Cover
Preface
About the Editor
Table of Contents
Contributors
Biographies of Contributors
Introduction
Volume I: Nuclear Engineering Fundamentals
     1: Neutron Cross Section Measurements
          1: Introduction
          2: History
          3: Currently Active Laboratories
               3.1 Time-of-Flight Laboratories
                    3.1.1 The Gaerttner LINAC Laboratory
                    3.1.2 The Los Alamos Neutron Science Center
                    3.1.3 The ORELA Laboratory at Oak Ridge National Laboratory
                    3.1.4 GELINA at the JRC-IRMM in Geel
                    3.1.5 The n_TOF Facility at CERN
                    3.1.6 The IREN Facility at Dubna
                    3.1.7 The PNF Laboratory at Pohang
                    3.1.8 Electron Linac at Kyoto University Research ReactorInstitute, KURRI
               3.2 Monoenergetic Fast Neutron Facilities
                    3.2.1 Neutron Energies Below 1: MeV
                    3.2.2 Neutron Energies in the MeV Region
                    3.2.3 Neutron Energies Near 14: MeV
                    3.2.4 Neutron Energies Above 30 MeV
          4: Neutron Cross Sections
               4.1 Introduction
               4.2 Total Cross Section
               4.3 Partial Cross Section
               4.4 Resonance Cross Section
               4.5 High Energy Cross Section
          5: Cross Section Measurements
               5.1 Thermal Energy Region
                    5.1.1 Thermal Flux Averaged Cross Section
               5.2 Resonance Energy Region
               5.3 Unresolved Resonance and Continuum Energy Region
               5.4 The Neutron Time of Flight Method
                    5.4.1 Neutron Density and Flux Distributions at Thermal Energies
               5.5 Surrogate Reactions
               5.6 Cross Section Standards
          6: Nuclear Resonances and the R-Matrix Formalism
               6.1 Introduction
                    6.1.1 Channel Representation
                    6.1.2 The Wave Function in the External Region
                    6.1.3 The Collision Matrix U
                    6.1.4 The Relation Between the Cross Sections andthe Collision Matrix U
                    6.1.5 The Wave Function in the Internal Region
                    6.1.6 The Relation Between the R-Matrix and the Collision Matrix U
               6.2 Approximations of the R-Matrix
                    6.2.1 The Breit–Wigner Single Level Approximation
                    6.2.2 The Breit–Wigner Multi Level Approximation
                    6.2.3 The Reich–Moore Approximation
               6.3 Average Cross Sections
          7: Concluding Remarks
          References
     2: Evaluated Nuclear Data
          1: Evaluation Methodology for Neutron Data
               1.1 Basic Ingredients
               1.2 Thermal and Resolved Resonance Region
                    1.2.1 Thermal Energy Region
                    1.2.2 Westcott Factors and Resonance Integrals
                    1.2.3 Resolved Resonance Energy Region
               1.3 Unresolved Resonance Region
               1.4 Fast Neutron Region
                    1.4.1 Optical Model and Direct Reactions
                    1.4.2 Compound Nucleus Decay
                    1.4.3 Width Fluctuation Correction
                    1.4.4 Preequilibrium Models
                    1.4.5 Light Nuclei
               1.5 Fission
                    1.5.1 Fission Modeling
                    1.5.2 Prompt Fission Neutron Spectra
                    1.5.3 Peculiarities of Fission Cross Section Evaluation
          2: Neutron Data for Actinides
               2.1 235U Evaluation
                    2.1.1 235U, Unresolved Resonance Region
                    2.1.2 235U, Fast Neutron Region
               2.2 238U Evaluation
                    2.2.1 238U, Resolved and Unresolved Resonance Region
                    2.2.2 238U, Fast Neutron Region
               2.3 239Pu Evaluation
                    2.3.1 239Pu, Resonance Region
                    2.3.2 239Pu, Fast Neutron Region
               2.4 232Th Evaluation
               2.5 Minor Actinides
                    2.5.1 233U Evaluation
                    2.5.2 232,234,236,237,239,240,241U Evaluations
               2.6 Thermal Constants
               2.7 Nubars
               2.8 Delayed Neutrons
                    2.8.1 Fission-Product Delayed Neutrons
                    2.8.2 235U Thermal nud
               2.9 Fission Energy Release
                    2.9.1 Nuclear Heating
          3: Neutron Data for Other Materials
               3.1 Light Nuclei
               3.2 Structural Materials
                    3.2.1 Evaluations of Major Structural Materials
                    3.2.2 New Evaluations for ENDF/B-VII.0
               3.3 Fission Products
                    3.3.1 Priority Fission Products
                    3.3.2 Complete Isotopic Chains
                    3.3.3 Specific Case of 90Zr
                    3.3.4 Remaining Fission Products
          4: Covariances for Neutron Data
               4.1 Evaluation Methodology
                    4.1.1 Resonance Region
                         SAMMY Covariance Method
                         Atlas Covariance Method
                         Low-Fidelity Covariance Method
                    4.1.2 Fast Neutron Region
                         EMPIRE-KALMAN Covariance Method
               4.2 Sample Case: Gd
               4.3 Major Actinides
                    4.3.1 233,235,238U Covariances
                    4.3.2 239Pu Covariances
                    4.3.3 232Th Covariances
               4.4 Covariance Libraries
                    4.4.1 Low-Fidelity Covariance Library
                    4.4.2 SCALE-6: Covariance Library
                    4.4.3 AFCI Covariance Library
          5: Validation of Neutron Data
               5.1 Criticality Testing
               5.2 Fast U and Pu Benchmarks
               5.3 Thermal U and Pu Benchmarks
                    5.3.1 235U Solution Benchmarks
                    5.3.2 U Fuel Rod Benchmarks
                    5.3.3 Pu Solution and MOX Benchmarks
               5.4 Conclusions from Criticality Testing
               5.5 Delayed Neutron Testing, eff
               5.6 Reaction Rates in Critical Assemblies
               5.7 Shielding and Pulsed-Sphere Testing
               5.8 Testing of Thermal Values and Resonance Integrals
          6: Other Nuclear Data of Interest
               6.1 Fission Yields
               6.2 Thermal Neutron Scattering
                    6.2.1 H2O and D2O
                    6.2.2 O in UO2: and U in UO2
                    6.2.3 H in ZrH
                    6.2.4 Other Modified Materials
               6.3 Decay Data
                    6.3.1 Decay Heat Calculations
          7: Evaluated Nuclear Data Libraries
               7.1 Overview of Libraries
                    7.1.1 General Purpose Libraries
                    7.1.2 Special Purpose Libraries
                    7.1.3 Derived Libraries
               7.2 ENDF-6: Format
               7.3 ENDF/B-VII.0 (USA, 2006)
                    7.3.1 Overview of the ENDF/B-VII.0 Library
                    7.3.2 Processing and Data Verification
               7.4 JEFF-3.1 (Europe, 2005)
               7.5 JENDL-3.3 (Japan, 2002)
               7.6 Web Access to Nuclear Data
          Acknowledgments
          References
     3: Neutron Slowing Down and Thermalization
          1: Thermal Neutron Scattering
               1.1 Introduction
               1.2 Chemical Binding
               1.3 Coherent and Incoherent Scattering
               1.4 The Quantum Mechanical Scattering Function
               1.5 The Intermediate Scattering Function
               1.6 Detailed Balance
               1.7 The Scattering Law
               1.8 The Phonon Expansion
               1.9 The Short Collision Time Approximation
               1.10 Diffusive Translations
               1.11 Discrete Oscillators
               1.12 Incoherent Elastic Scattering
               1.13 Coherent Elastic Scattering
               1.14 Example of Thermal Scattering in Graphite
               1.15 Example of Thermal Scattering in Water
               1.16 Example for Thermal Scattering in Heavy Water
               1.17 Example for Thermal Scattering in Zirconium Hydride
               1.18 Using the ENDF/B Thermal Scattering Evaluations
          2: Neutron Thermalization
               2.1 Introduction
               2.2 Monte Carlo Simulations of Neutron Thermalization
               2.3 Discrete Ordinates Methods
                    2.3.1 SN Theory
                    2.3.2 Transport Corrections
                    2.3.3 Fission Source
                    2.3.4 The Eigenvalue Iteration
                    2.3.5 SN Data Requirements
                    2.3.6 Example for HST42-5
                    2.3.7 Preparing SN Cross-Section Data
                    2.3.8 Example for an Infinite Pin-Cell Lattice
                    2.3.9 Monte Carlo vs. Multigroup
               2.4 Collision Probability Methods
               2.5 Size Effects in Thermalization
          3: Steady-State Slowing Down
               3.1 Introduction
               3.2 Slowing-Down Cross Sections
               3.3 Spectra for Elastic Downscatter
               3.4 Spectra for Inelastic Downscatter
               3.5 Resonance Cross Sections
                    3.5.1 Single-Level Breit–Wigner Representation
                    3.5.2 Multi-Level Breit–Wigner Representation
                    3.5.3 Reich–Moore Representation
                    3.5.4 Reich–Moore-Limited Representation
                    3.5.5 Angular Distributions
                    3.5.6 Resonance Reconstruction and Doppler Broadening
                    3.5.7 Thermal Constants
               3.6 Resonance Slowing Down
               3.7 Flux Calculations
               3.8 Intermediate Resonance Self-Shielding
               3.9 Unresolved Resonance Range Methods
          4: Time and Space in Slowing Down
               4.1 Introduction
               4.2 Time Dependence of the Energy Spectrum
               4.3 Time Dependence of the Spatial Distribution
               4.4 Eigenvalues and Eigenfunctions
               4.5 Analytic Age Theory
          5: Concluding Remarks and Outlook
          References
     4: Nuclear Data Preparation
          1: Overview
               1.1 Introduction
               1.2 The ENDF/B Format
                    1.2.1 ENDF/B Tables and Interpolation
               1.3 The Importance of Nuclear Data-Processing Codes
               1.4 First-Order Approximations: Space, Energy, and Time
               1.5 Basic Equations
               1.6 Species of Particles
               1.7 Evaluated Data
                    1.7.1 Neutron-Interaction Data
                         Secondary-Neutron Distributions
                    1.7.2 Neutron-Induced Photon Production
                    1.7.3 Photon Interaction Data
               1.8 Approximate Methods
                    1.8.1 Monte Carlo Versus Deterministic Codes
                    1.8.2 Continuous Energy
                    1.8.3 Multigroup
               1.9 Summary
          2: Reconstruction of Energy-Dependent Cross Sections
               2.1 Introduction
               2.2 Representation of Cross Sections
               2.3 Tabulated Cross Sections
                    2.3.1 Linearized Cross Sections
               2.4 Reconstructing the Contribution of Resonances
                    2.4.1 The Resolved-Resonance Region
                    2.4.2 Unresolved-Resonance Region
                    2.4.3 Adding Resonance and Background Cross Sections
                    2.4.4 Output Format
          3: Doppler Broadening
               3.1 Introduction
                    3.1.1 What Causes Doppler Broadening?
               3.2 The Doppler-Broadening Equation
                    3.2.1 Mathematical Interpretation
               3.3 Methods of Solution
                    3.3.1 Kernel Broadening
                    3.3.2 Tabulated Broadened Cross Sections
                    3.3.3 TEMPO and Psi–Chi Methods
                    3.3.4 Mathematical Comparisons
               3.4 Numerical Results
                    3.4.1 Low Energies
                    3.4.2 Resonance Region
                    3.4.3 High Energies
          4: Self-Shielding
               4.1 Introduction
               4.2 Narrow, Intermediate, and Wide Resonances
                    4.2.1 Narrow Resonances
                    4.2.2 Wide Resonances
                    4.2.3 Intermediate Resonances
               4.3 Cross-section Dependence of Flux
               4.4 Computation of Multigroup Cross Sections
                    4.4.1 Tabulated Cross Sections
                    4.4.2 Linearly Interpolable Data
                    4.4.3 Solution
                    4.4.4 Direct Integration
               4.5 Comparison of Results
          5: Transfer Matrix
               5.1 Introduction
               5.2 Solution
                    5.2.1 Uncorrelated Distributions
                    5.2.2 Angular Distributions
                    5.2.3 Energy Distributions
                    5.2.4 Correlated Distributions
                    5.2.5 Solution of the Inner Integral
                    5.2.6 Thermal-Scattering Law Data: S(,)
          6: Group Collapse
               6.1 Introduction
               6.2 Noncoincident-Group Boundaries
          7: The Multiband Method
               7.1 Introduction
               7.2 Multiband Equations
               7.3 Multiband Parameters
               7.4 Solution for Band Parameters
                    7.4.1 Analytical Solution for Two Bands
                    7.4.2 Generalization to N Bands
                    7.4.3 How Many Bands are Required?
               7.5 Transfer Matrix
               7.6 Boundary Condition
               7.7 Example Results
                    7.7.1 Theoretical Cases
                    7.7.2 Bramblett–Czirr Plate Measurements
                    7.7.3 Criticality Calculations
                    7.7.4 Shielding Calculations
                    7.7.5 Fusion Reactor Blanket
               7.8 Conclusions
          Acknowledgments
          References
     5: General Principles of Neutron Transport
          1: Introduction
          2: Derivation of the Neutron Transport (Linear Boltzmann) Equation
               2.1 Independent Variables
               2.2 The Basic Physics of Neutron Transport
               2.3 The Angular Neutron Density and Angular Flux
               2.4 Internal and Boundary Sources
               2.5 The Time-Dependent Equations of Neutron Transport
               2.6 Time-Dependent Neutron Transport Without Delayed Neutrons
               2.7 The Steady-State Neutron Transport Equation
               2.8 k-Eigenvalue Problems
               2.9 The Monoenergetic Neutron Transport Equation
               2.10 Mathematical Issues
                    2.10.1 Existence, Uniqueness, and Nonnegativity of Transport Solutions
                    2.10.2 The nth Collided Fluxes
                    2.10.3 Smoothness of the Angular Flux
               2.11 Generalizations of the Neutron Transport Equation
                    2.11.1 Reflecting Boundaries
                    2.11.2 Periodic Boundaries
                    2.11.3 Anisotropic Sources
                    2.11.4 Coupled Neutron/Photon Transport
                    2.11.5 Temperature-Dependent Cross Sections
                    2.11.6 Advection and Diffusion of Fission Products
               2.12 Limitations of the Neutron Transport Equation
               2.13 Discussion
          3: The Transport Equation in Special Geometries
               3.1 3-D Cartesian Geometry
               3.2 1-D Planar Geometry
               3.3 2-D (X,Y)-Geometry
               3.4 1-D Spherical Geometry
               3.5 3-D normalnormal(r, thetav, z)-Geometry
               3.6 2-D normalnormal(r,z)-Geometry
               3.7 1-D Cylindrical Geometry
               3.8 Discussion
          4: Integral Equation for Neutron Transport
               4.1 Integral Equation for the Angular Flux
               4.2 The Integral Equation for the Scalar Flux
               4.3 Discussion
          5: The Adjoint Neutron Transport Equation
               5.1 Definitions
               5.2 Illustrative Example
               5.3 The Adjoint Transport Equation
               5.4 Adjoint Flux as an Importance Function
                    5.4.1 Source-Detector Problems
               5.5 Green's Functions
               5.6 Discussion
          6: The Multigroup and One-Speed Neutron Transport Equations
               6.1 The Continuous-Energy Problem
               6.2 The Multigroup Transport Equations
               6.3 The Within-Group and One-Group Transport Equations
               6.4 Discussion
          7: The Age and Wigner Approximations
               7.1 The Infinite-Medium Neutron Spectrum Equation
               7.2 The "Conservative'' Form of the Neutron Transport Equation
               7.3 The Age Approximation
               7.4 The Wigner Approximation
               7.5 Discussion
          8: The Diffusion Approximation
               8.1 Derivation of the Diffusion Equation
               8.2 Homogenized Diffusion Theory
               8.3 Spherical Harmonic (PN) and Simplified Spherical Harmonic (SPN)Approximations
               8.4 Discussion
          9: The Point Kinetics Approximation
               9.1 Preliminaries
               9.2 The Scaled Transport and Neutron Precursor Equations
               9.3 Asymptotic Derivation of the Point Kinetics Equations
               9.4 Discussion
          10: Computational Neutron Transport
               10.1 Monte Carlo Methods
               10.2 Deterministic Methods
               10.3 Hybrid Monte Carlo/Deterministic Methods
               10.4 Discussion
          11: Concluding Remarks
          References
     6: Nuclear Materials and Irradiation Effects
          1: Introduction
               1.1 Definition of Nuclear Materials
               1.2 Radiation Fluxes in Nuclear Reactors
          2: Radiation Damage
               2.1 Irradiation Damage by Neutrons
                    2.1.1 Inelastic Interactions: Chemical Changes
                    2.1.2 Elastic Interactions by Neutrons
                    2.1.3 Damage Cross Section
                    2.1.4 Computation of Damage for Power Reactors
                    2.1.5 Time Evolution of the Point Defects
                         PD Clustering
               2.2 Effects on Microstructure and Engineering Properties
                    Physical Properties
                         Diffusion Under Irradiation
                    2.2.1 PD Clustering, Dislocation Loop, and Cavities
                    2.2.2 Segregations, Phase Transformations, and Amorphization
                         Solute Transport and Segregations
                         Phase Diagrams Under Irradiation
                    2.2.3 Computational Techniques for Nuclear Material Science
                         First Principle (Ab Initio)
                         Molecular Dynamics
                         Monte Carlo
                    2.2.4 Impact of Irradiation on Engineering Design Properties
                         Thermoelastic Properties
                         Radiation Hardening and Plastic Behavior
                         Embrittlement and Reduction in Ductility
                         Irradiation Creep
               2.3 Irradiation Damage in Ceramics
                    2.3.1 General Aspects
                    2.3.2 Irradiation Damage
                    2.3.3 Changes in Microstructure
                    2.3.4 Change in Properties
               2.4 Irradiation Damage by Photons and Electrons
                    2.4.1 Radiation-Induced Conductivity in Ceramics
                    2.4.2 Radiolysis: Water and Polymers
                         Mechanisms of Radiolysis
                         Technological Impact ofWater Radiolysis for the Nuclear industry
                         Radiolysis in Polymers
          3: Impact of Irradiation Damage on Structural Material Behavior
               3.1 Ferritic Steels (LWR Pressure Vessel)
                    3.1.1 General Aspects
                    3.1.2 Microstructural Aspects
                    3.1.3 Pressure Vessel Steel Embrittlement
                         Fracture Mechanics
                         Master Curve and New Issues
               3.2 Austenitic Stainless Steels (LWR Internals)
                    3.2.1 Changes in Microstructure and Mechanical Properties
                         Irradiation-Assisted Stress Corrosion Cracking
                    3.2.2 Radiation-Induced Segregation
          4: Reactor Core Materials
               4.1 Stainless Steels in SFR
                    4.1.1 Changes in Microstructure
                    4.1.2 Swelling
                    4.1.3 Irradiation Hardening and Irradiation Creep
                         Irradiation Hardening
                         Irradiation Creep
                    4.1.4 Development of Low Swelling Alloys
               4.2 Zirconium Alloys in Water Reactors
                    4.2.1 Zirconium Alloys: Zircaloy and Zr-Nb
                         Industrial Alloys
                         Microstructure
                         Deformation Processing and Textures
                         Mechanical Properties
                    4.2.2 Dislocation Loops: Growth and Irradiation Creep
                         Irradiation Effects in the Zr Matrix
                         Irradiation Effects on Second Phases
                         Irradiation Growth
                         Irradiation Creep
                    4.2.3 Postirradiation Plastic Behavior
                    4.2.4 Corrosion Behavior and Effects of Irradiation on Corrosion
                         General Corrosion Behavior
                         Hydrogen Pick-Up
                    4.2.5 Interaction with Fission Products I-SCC and PCI Failure
               4.3 Carbon and Graphite
                    4.3.1 Nuclear Graphite
                    4.3.2 Behavior Under Irradiation
                    4.3.3 Creep and Wigner Effect
                    4.3.4 Corrosion
          5: Fusion Reactor Materials
               5.1 Specific Environment of the Fusion Reactors
               5.2 Plasma Facing and High Heat Flux Components
               5.3 First Wall and the Blanket Structures
               5.4 Blankets and Tritium Breeding Materials
          6: Corrosion in Nuclear Environments
          7: Prospects
          List of Acronyms
          Appendix
          Industrial Steels for Reactor Design
          References
     7: Mathematics for Nuclear Engineering
          1: Finite-Dimensional Vector Spaces
               1.1 Vectors: Definitions and Operations
               1.2 Matrices: Basic Definitions and Properties
          2: Elements of Functional Analysis
               2.1 Operators in Vector Spaces
               2.2 Differential Calculus
          3: Special Functions
               3.1 The Gamma Function:Gamma (z)
               3.2 The Beta Function
               3.3 The psi Function
               3.4 The Generalized Zeta and Riemann's Zeta Functions
               3.5 Bernoulli's Numbers and Polynomials
          4: Bessel Functions
               4.1 Bessel Functions of General Order
               4.2 Modified Bessel Functions of General Order
               4.3 Bessel Functions of Integer Order
               4.4 Modified Bessel Functions of Integer Order
               4.5 Spherical Bessel Functions
               4.6 Miscellaneous Formulas
               4.7 Zeros of Bessel Functions
               4.8 Fourier-Bessel and Dini Series
               4.9 Asymptotic Expansions
               4.10 Integrals
               4.11 Additional Theorems and Related Series
          5: Associated Legendre Functions
               5.1 Differential Equation
               5.2 Asymptotic Series for Large Values of nu
               5.3 Recursion Relations
               5.4 Spherical Functions (Associated Legendre Functions withIntegral Indices)
          6: Orthogonal Polynomials
               6.1 Legendre Polynomials: Pn(z)
               6.2 Gegenbauer Polynomials: Clamdan(t)
               6.3 Chebyshev Polynomials Tn(x) and Un(x)
               6.4 Hermite Polynomials Hn(x)
               6.5 Laguerre Polynomials
          7: Probability Theory and Statistical Estimation
               7.1 Introduction
               7.2 Multivariate Probability Distributions
               7.3 Expectations and Moments
               7.4 Variance, Standard Deviation, Covariance, and Correlation
               7.5 Commonly Encountered Probability Distributions
               7.6 Central Limit Theorem
               7.7 Statistical Estimation
               7.8 Stationary Random Sequence and White Noise
          8: Fourier Transforms
               8.1 Fourier Transforms of Continuous Functions
               8.2 Properties of Fourier Transform
               8.3 Fourier Transform of Discrete Functions
               8.4 Fourier Series
          Bibliography
Volume II: Reactor Design
     8: Multigroup Neutron Transport and Diffusion Computations
          1: The Steady-State Boltzmann Equation
               1.1 The Integro-Differential Form of the Transport Equation
               1.2 The Characteristic Form of the Transport Equation
               1.3 The Integral Form of the Transport Equation
               1.4 Boundary and Continuity Conditions
               1.5 The Steady-State Source Density
               1.6 The Transport Correction
               1.7 Multigroup Discretization
          2: The First-Order Streaming Operator
               2.1 Cartesian Coordinate System
               2.2 Cylindrical Coordinate System
               2.3 Spherical Coordinate System
          3: The Spherical Harmonics Method
               3.1 The Pn Method in 1D Slab Geometry
                    3.1.1 Discretization in Angle
                    3.1.2 Boundary Conditions
                    3.1.3 Difference Relations
               3.2 The Pn Method in 1D Cylindrical Geometry
                    3.2.1 Discretization in Angle
                    3.2.2 Boundary Conditions
                    3.2.3 Difference Relations
               3.3 The Pn Method in 1D Spherical Geometry
                    3.3.1 Discretization in Angle
                    3.3.2 Boundary Conditions
                    3.3.3 Difference Relations
               3.4 The Simplified Pn Method in 2D Cartesian Geometry
                    3.4.1 Discretization in Angle
                    3.4.2 Difference Relations
          4: The Collision Probability Method
               4.1 The Interface Current Method
               4.2 Scattering-Reduced Matrices and Power Iteration
               4.3 Slab Geometry
               4.4 Cylindrical 1D Geometry
               4.5 Spherical 1D Geometry
               4.6 Unstructured 2D Finite Geometry
          5: The Discrete Ordinates Method
               5.1 Quadrature Sets in the Method of Discrete Ordinates
               5.2 The Difference Relations in 1D Slab Geometry
               5.3 The Difference Relations in 1D Cylindrical Geometry
               5.4 The Difference Relations in 1D Spherical Geometry
               5.5 The Difference Relations in 2D Cartesian Geometry
               5.6 Synthetic Acceleration
          6: The Method of Characteristics
               6.1 The MOC Integration Strategy
               6.2 Unstructured 2D Finite Geometry
               6.3 The Algebraic Collapsing Acceleration
          7: The Steady-State Diffusion Equation
               7.1 The Fick Law
               7.2 Continuity and Boundary Conditions
               7.3 The Finite Homogenous Reactor
                    7.3.1 Cartesian Coordinate System
                    7.3.2 Spherical Coordinate System
                    7.3.3 Cylindrical Coordinate System
               7.4 The Heterogenous 1D Slab Reactor
                    7.4.1 Two-Region Example
          8: Discretization of the Neutron Diffusion Equation
               8.1 Mesh-Corner Finite Differences
               8.2 Mesh-Centered Finite Differences
               8.3 A Primal Variational Formulation
               8.4 The Lagrangian Finite-Element Method
               8.5 The Analytic Nodal Method in 2D Cartesian Geometry
          Appendix: Tracking of 1D and 2D Geometries
               1: Tracking of 1D Cylindrical and Spherical Geometries
               2: The Theory Behind sybt1d
               3: Tracking of 2D Square Pincell Geometries
               4: The Theory Behind sybt2d
          References
     9: Lattice Physics Computations
          1: Overview
               1.1 Introduction
               1.2 Brief History
               1.3 Cross Section Library
               1.4 Entering the Resonance Tables
                    1.4.1 Determining Microscopic Background Cross Sections
                         Volume Component
                         Surface Component
                    1.4.2 Resonance Interference Effects
               1.5 Condensation Scheme
                    1.5.1 Pin-Cell Calculations
                    1.5.2 Coupling Calculation
               1.6 Assembly Fine-Mesh Transport Calculation
                    1.6.1 The CCCP Method
                    1.6.2 The Method of Characteristics
               1.7 Fundamental Mode Calculation
               1.8 Gamma Transport Calculation
               1.9 Power Distribution Calculation
               1.10 Burnup Calculation
               1.11 Edits
               1.12 Summary
          2: Cross Section Library
               2.1 Objective
               2.2 Choice of Energy Group Structure
                    2.2.1 WIMS 69: Groups
                    2.2.2 XMAS 172: Groups
                    2.2.3 SHEM 281: Groups
                    2.2.4 Other Energy Group Structures
               2.3 Cross Sections Used in Lattice Physics Computations
               2.4 Cross Section Processing
                    2.4.1 Generation of Multigroup Cross Section Data
                         MODER
                         RECONR
                         BROARDR
                         THERMR
                         UNRESR
                         GROUPR
                         MATXSR
                         OtherModules
                         Some Notes on NJOY
                    2.4.2 Execution Control of NJOY
                    2.4.3 Post-Processing for Cross Section Library
                         Absorption Cross Section
                         Nu-Value and Fission Spectrum
                         ScatteringMatrix
                         Editing for Cross Section Library
               2.5 Tabulation and Contents of Cross Section Library
                    2.5.1 General File Format
                    2.5.2 Nuclide Identifiers
                    2.5.3 Dependency of Cross Sections
                    2.5.4 General Data
                    2.5.5 One-Dimensional Data
                         Elimination of Zero Elements
                         Storage of Variations in Cross Sections
                         Reduction of Grid Points for Temperature/Background Cross Sections
                    2.5.6 Two-Dimensional Data
                    2.5.7 Burnup-Related Data
                    2.5.8 Gamma Cross Section Library
               2.6 Summary*6pt
          3: Resonance Treatment
               3.1 Objective
               3.2 Effective Cross Sections
               3.3 Physics of Self-Shielding and Major Resonance Calculations
                    3.3.1 Physics of Self-Shielding
                    3.3.2 Ultrafine Energy Group Calculation
                    3.3.3 Equivalence Theory
                    3.3.4 Subgroup Method
               3.4 Resonance Self-Shielding in a Homogeneous System
                    3.4.1 Slowing Down of Neutrons in a Homogeneous System
                    3.4.2 Narrow Resonance Approximation
                    3.4.3 Wide Resonance Approximation
                    3.4.4 Intermediate Resonance Approximation
               3.5 Resonance Self-Shielding in a Heterogeneous Systems
                    3.5.1 Neutron Slowing Down in a Heterogeneous Isolated System
                         Reciprocity Theorem
                         Estimation of Escape Probability and Average Chord Length
                         Approximations of Neutron Spectrum in a Heterogeneous System
                    3.5.2 Equivalence Theory
                    3.5.3 Various Approximations for Escape Probability
                         Incorporation of the Bell Factor
                         N-Terms Rational Approximations
                         Carlvik’s Two-TermRational Approximation
                         Evaluation of the Effective Cross Section fromN-Term Rational Approximation
                         Resonance Integral and Effective Cross Section
                    3.5.4 Neutron Slowing Down in a Heterogeneous Lattice System
                         Formulation of Slowing Down Equation in Lattice System
                         Dancoff Correction or Dancoff Factor
                         Dancoff Correction and Collision Probability in the Moderator
                         Dancoff Correction and Escape Probability for an Isolated Fuel Lump
                         Equivalence Theory in Lattice System
                    3.5.5 Calculation of the Dancoff Factor and Background Cross Sections
                         Calculation of Dancoff Factor Using the Collision Probability Method
                         Neutron Current Method for Dancoff Correction Calculation
                         Enhanced Neutron Current Method for Background Cross Section Evaluation
                    3.5.6 Stamm'ler's Method for a Heterogeneous Lattice System
                    3.5.7 Potential Limitations of the Equivalence Theory
               3.6 Tabulation of Self-Shielding Factors
                    3.6.1 Cross Section Processing and Effective Cross Sections
                    3.6.2 Interpolation of Self-Shielding Factor Table
               3.7 Ultrafine Group Method
                    3.7.1 Homogeneous System
                    3.7.2 Heterogeneous System
                    3.7.3 Limitations of the Ultrafine Energy Groups Method
               3.8 Subgroup Method
                    3.8.1 General Concept
                    3.8.2 Direct Approach
                    3.8.3 Probability Table Approach
                    3.8.4 Fitting Method
                    3.8.5 Moment Method
                    3.8.6 Improvements in the Probability Table Approach
               3.9 Other Methods
                    3.9.1 Tone's Method
                    3.9.2 The Stoker–Weiss Method and the Space-Dependent DancoffMethod (SDDM)
                         The Stoker–Weiss Method
                         Space-Dependent DancoffMethod (SDDM)
               3.10 Resonance Overlap Effect
                    3.10.1 Overview
                    3.10.2 Resonance Interference Factor (RIF) Table
                    3.10.3 Utilization of an Ultrafine Energy Group Cross Section
               3.11 Other Topics in Resonance Calculations
                    3.11.1 Effective Temperature Used in Resonance Calculation
                    3.11.2 Temperature Distribution in a Resonance Region
                    3.11.3 Treatment of Number Density Distribution in a Pellet
                    3.11.4 Resonance Calculation for Non-Heavy Nuclides
                    3.11.5 Verification and Validation of Resonance Calculation Model
               3.12 Summary
          4: Energy Condensation Scheme
               4.1 Introduction
               4.2 Pin-Cell Spectral Calculations
                    4.2.1 General Theory
                    4.2.2 The Method of Collision Probabilities in Slab Geometry
                    4.2.3 The Method of Collision Probabilities in Cylindrical Geometry
                    4.2.4 White Boundary Conditions
                    4.2.5 Buffer Zone
                    4.2.6 Numerics of the Pin-Cell Spectral Calculation
               4.3 Coupling Calculation
                    4.3.1 The Method of Transmission Probabilities
                    4.3.2 Numerics of the Coupling Calculation
                    4.3.3 Solution to the Response Matrix Equations
                         Inner Iterations
                         Outer Iterations
                         Fundamental Mode Rebalance
                    4.3.4 Geometry of the Coupling Calculation
               4.4 Cross Section Condensation
               4.5 Sundries
          5: Fine-Mesh Assembly Calculation
               5.1 Introduction
               5.2 General Theory of the Method of Characteristics
                    5.2.1 Introduction
                    5.2.2 Solution to the Characteristics Form of the Transport Equation
               5.3 Quadrature Sets
                    5.3.1 Introduction
                    5.3.2 Azimuthal Angles
                    5.3.3 Polar Angles
               5.4 Geometry Routine
                    5.4.1 Introduction
                    5.4.2 Neutron Streaming and Symmetry in Slab Geometry
                    5.4.3 Ray Tracing in Slab Geometry
               5.5 Solution to the Characteristics Equation
                    5.5.1 Introduction
                    5.5.2 Initialization of the Flux
                    5.5.3 Calculating the Source Term
                         Scattering Source
                         Fission Source
                         External Source
                         Total Source for a Non-Multiplying System
                         Total Source for a Multiplying System
                    5.5.4 Boundary Conditions
                         Periodic Boundary Conditions
                         Reflective Boundary Conditions
                    5.5.5 Convergence
                         Convergence of the Angular Flux
                         Convergence of the Scalar Flux
                         Convergence of the Multiplication Factor
                    5.5.6 Accelerating the Flux Convergence
                         Energy Acceleration
                         Spatial Acceleration
               5.6 Cylindrical Geometry
                    5.6.1 Introduction
                    5.6.2 Choosing the Azimuthal Angles of Motion
                         Even Angle Distribution
                         Even Boundary Distribution
                    5.6.3 An Alternative Tracking Approach
                         General Theory
                         Example
                         Track Adjustments
                    5.6.4 Modification to the Characteristics Equation
               5.7 Two-Dimensional Geometry
               5.8 Mesh Subdivisions for Two-Dimensional Problems
                    5.8.1 Assigning Material Regions
                    5.8.2 Meshing
                    5.8.3 Defining Various Cell Types
                    5.8.4 Meshing of Control Blade Cells
                    5.8.5 Final Mesh Layout
               5.9 Two-Dimensional Ray Tracing
                    5.9.1 The Cyclic Tracking Approach
                    5.9.2 The Macro-Band Approach
               5.10 Quadrature Sets for Two-Dimensional LWR Lattice Calculations
                    5.10.1 Quadratures for Modeling Polar Motion
                    5.10.2 Quadratures for Modeling Azimuthal Motion
               5.11 Acceleration Schemes for Two-Dimensional Calculations
                    5.11.1 Coarse Mesh Rebalance
                    5.11.2 Coarse Mesh Finite Difference
               5.12 Treating Very Thin Cylindrical Regions
               5.13 Final Comments
          6: Burnup Calculation
               6.1 Objective
               6.2 The Physics of Burnup and its Modeling
                    6.2.1 Phenomena during Burnup
                         Depletion of Fissile Nuclides (a)
                         Conversion fromFertile Nuclide to Fissile Nuclide (b)
                         Production of Fission Products (c)
                         Decay
                         Transmutation of Nuclides due to Neutron Absorption
                    6.2.2 Burnup Chain
                         Design and Setup of Burnup Chain
                         Evaluation of Fission-Product Yield
                         Estimation of Cross Sections and Yields for Pseudo Fission Products
                         Branching Ratio
                    6.2.3 Burnup Equation
                         Burnup of a Fissile Nuclide
                         Burnup Equation with Multiple Nuclides
                         Burnup Equation in General Form
                    6.2.4 Burnup, Burnup Time, and Normalization of Neutron Flux
                         Burnup and Burnup Time
                         Normalization of Neutron Flux
               6.3 Numerical Scheme
                    6.3.1 Potential Causes of Error in a Numerical Solution
                         Error in Reaction Rate (Production, Absorption, and Decay Rates)
                         Temporal Discretization Error of the Differential Equation of Burnup Equation
                         Temporal Discretization Error in Reaction Rates of Burnup Equation
                         Normalization Error of Thermal Output
                         Error in Initial Composition of Fuel
                    6.3.2 General Remarks on Numerical Solutions for the Burnup Equation
                    6.3.3 The Euler Method
                    6.3.4 The Runge–Kutta Method
                    6.3.5 The Matrix Exponential Method
                    6.3.6 The Matrix Decomposition Method
                    6.3.7 Bateman Method
                    6.3.8 The Padé Approximation
                    6.3.9 The Krylov Subspace Method
                    6.3.10 Numerical Example
                    6.3.11 Predictor–Corrector Method
                    6.3.12 Sub-Step Method
                         Reduction of Temporal Discretization Error
                         Power Normalization during Burnup Step
                    6.3.13 Cooling Calculation
                         135I.(Half-Life 6.7 h).135Xe
                         149Pm.(Half-Life 54: h).149Sm
                         239Np.(Half-Life 2.4 days).239Pu
                         148mPm.(Half-Life 41: days).148Sm
                         148Pm.(Half-Life 2.6 years).148Sm
                         155Eu.(Half-Life 4.7 years).155Gd
                         241Pu.(Half-Life 14.4 years).241Am
               6.4 Burnup in Gadolinia-Bearing Fuel
                    6.4.1 Onion-Skin Effect
                    6.4.2 Asymmetry Effect in Gadolinium Depletion
                    6.4.3 Various Numerical Techniques for Gadolinium Depletion
               6.5 Summary
          7: Case Matrix
               7.1 Introduction
               7.2 Cross Section Dependencies in BWRs
                    Historical Void
                    Exposure
                    Void Coefficient
                    Fuel Temperature Coefficient
                    Moderator Temperature Coefficient
                    Control Blade Coefficient
                    Control Blade History Coefficient
                    Fuel Temperature History Coefficient
                    Shutdown Cooling Coefficient
               7.3 Cross Section Dependencies in PWRs
                    Historical Moderator Temperature
                    Historical Boron Concentration
                    Moderator Temperature Coefficient
                    Boron Coefficient
               7.4 Summary
          8: Edits
               8.1 Nomenclature
               8.2 Various Edits
               8.3 Neutron Balance
          9: Concluding Remarks
          References
     10: Core Isotopic Depletion and Fuel Management
          1: Burnup and Conversion
               1.1 Introduction
               1.2 The Bateman Equation
               1.3 Solution of the Bateman Equation
               1.4 Results of Burnup Calculations
               1.5 The Breeding (Conversion) Ratio
               1.6 Transmutation
               1.7 Burnable Poisons
          2: Transient Fission Products
               2.1 Transient Fission Product Equations
               2.2 Xenon Transient Phenomena and Control
                    2.2.1 Global Phenomena
                    2.2.2 Spatial Phenomena
          3: Nuclear Fuel Management
               3.1 Introduction
               3.2 Out-of-Core Nuclear Fuel Management
               3.3 LWR In-Core Nuclear Fuel Management
                    3.3.1 LWR Loading Pattern Selection
                    3.3.2 LWR Control Rod Programming Selection
                    3.3.3 LWR Lattice and Assembly Selection
               3.4 Non-LWR In-Core Nuclear Fuel Management
                    3.4.1 Introduction
                    3.4.2 Heavy Water Reactors
                    3.4.3 Very High Temperature Gas-Cooled Reactors
                    3.4.4 Advanced Recycle Reactor
               3.5 Applications of Mathematical Optimization in Nuclear FuelManagement
                    3.5.1 Introduction
                    3.5.2 Mathematical Optimization Approaches Utilized for Nuclear FuelManagement
                    3.5.3 Application of Mathematical Optimization to Out-of-Core Nuclear FuelManagement
                    3.5.4 Application of Mathematical Optimization to In-Core Nuclear FuelManagement
               3.6 Computational Design Sequences
                    3.6.1 Design Calculations Needed
                    3.6.2 Cross-Section Generation
                    3.6.3 Core Simulation
          4: Conclusions
          References
     11: Radiation Shielding and Radiological Protection
          1: Radiation Fields and Sources
               1.1 Radiation Field Variables
                    1.1.1 Direction and Solid Angle Conventions
                    1.1.2 Radiation Fluence
                    1.1.3 Radiation Current or Net Flow
                    1.1.4 Directional Properties of the Radiation Field
                    1.1.5 Angular Properties of the Flow and Flow Rate
               1.2 Characterization of Radiation Sources
                    1.2.1 General Considerations
                    1.2.2 Neutron Sources
                         Fission Sources
                         Photoneutrons
                         Neutrons from (,n) Reactions
                         Activation Neutrons
                         Fusion Neutrons
                    1.2.3 Gamma-Ray Sources
                         Radioactive Sources
                         Prompt Fission Gamma Photons
                         Gamma Photons from Fission Products
                         Capture Gamma Photons
                         Gamma Photons from Inelastic Neutron Scattering
                         Activation Gamma Photons
                    1.2.4 X-Ray Sources
                         Characteristic X Rays
                         Bremsstrahlung
                         X-Ray Machines
          2: Conversion of Fluence to Dose
               2.1 Local Dosimetric Quantities
                    2.1.1 Energy Imparted and Absorbed Dose
                    2.1.2 Kerma
                    2.1.3 Exposure
                    2.1.4 Local Dose Equivalent Quantities
                         Relative Biological Effectiveness
                         Linear Energy Transfer
                         Radiation Weighting Factor and Dose Equivalent
               2.2 Evaluation of Local Dose Conversion Coefficients
                    2.2.1 Photon Kerma, Absorbed Dose, and Exposure
                    2.2.2 Neutron Kerma and Absorbed Dose
               2.3 Phantom-Related Dosimetric Quantities
                    2.3.1 Characterization of Ambient Radiation
                    2.3.2 Dose Conversion Factors for Geometric Phantoms
                         Deep Dose Equivalent Index
                         Shallow Dose Equivalent Index
                         Ambient Dose Equivalent
                         Directional Dose Equivalent
                         Irradiation Geometries for Spherical Phantoms
                         Slab and Cylinder Phantoms
                    2.3.3 Dose Coefficients for Anthropomorphic Phantoms
                         Effective Dose Equivalent
                         Effective Dose
                    2.3.4 Comparison of Dose Conversion Coefficients
          3: Basic Methods in Radiation Attenuation Calculations
               3.1 The Point-Kernel Concept
                    3.1.1 Exponential Attenuation
                    3.1.2 Uncollided Dose from a Monoenergetic Point Source
                         Point Source in a Vacuum
                         Point Source in a Homogenous Attenuating Medium
                         Point Source with a Shield
               3.2 Uncollided Doses for Distributed Sources
                    3.2.1 The Superposition Procedure
                    3.2.2 Example Calculations for Distributed Sources
                         The Line Source
          4: Photon Attenuation Calculations
               4.1 The Photon Buildup-Factor Concept
               4.2 Isotropic, Monoenergetic Sources in Infinite Media
               4.3 Buildup Factors for Point and Plane Sources
                    4.3.1 Empirical Approximations for Buildup Factors
                         The Geometric Progression Approximation
                    4.3.2 Point-Kernel Applications of Buildup Factors
                         Line Source in an Infinite Attenuating Medium
               4.4 Buildup Factors for Heterogenous Media
                    4.4.1 Boundary Effects in Finite Media
                    4.4.2 Treatment of Stratified Media
               4.5 Broad-Beam Attenuation of Photons
                    4.5.1 Attenuation Factors for Photon Beams
                    4.5.2 Attenuation of Oblique Beams of Photons
                    4.5.3 Attenuation Factors for X-Ray Beams
                    4.5.4 The Half-Value Thickness
               4.6 Shield Heterogeneities
                    4.6.1 Limiting Case for Small Discontinuities
                    4.6.2 Small Randomly Distributed Discontinuities
          5: Neutron Shielding
               5.1 Neutron Versus Photon Calculations
               5.2 Fission Neutron Attenuation by Hydrogen
               5.3 Removal Cross Sections
               5.4 Extensions of the Removal Cross Section Model
                    5.4.1 Effect of Hydrogen Following a Nonhydrogen Shield
                    5.4.2 Homogenous Shields
                    5.4.3 Energy-Dependent Removal Cross Sections
               5.5 Fast-Neutron Attenuation Without Hydrogen
               5.6 Intermediate and Thermal Fluences
                    5.6.1 Diffusion Theory for Thermal Neutron Calculations
                    5.6.2 Fermi Age Treatment for Thermal and Intermediate-Energy Neutrons
                    5.6.3 Removal-Diffusion Techniques
                         Original Spinney Method
                         Improved Removal-Diffusion Methods
               5.7 Capture-Gamma-Photon Attenuation
               5.8 Neutron Shielding with Concrete
                    5.8.1 Concrete Slab Shields
                         Effect of Water Content
                         Effect of Slant Incidence
                         Effect of the Aggregate
                         Effect of the Fluence-to-Dose Conversion Factor
          6: The Albedo Method
               6.1 Differential Number Albedo
               6.2 Integrals of Albedo Functions
               6.3 Application of the Albedo Method
               6.4 Albedo Approximations
                    6.4.1 Photon Albedos
                    6.4.2 Neutron Albedos
                         Secondary-Photon Albedos
          7: Skyshine
               7.1 Approximations for the LBRF
                    7.1.1 Photon LBRF Approximation
                    7.1.2 Neutron LBRF Approximation
               7.2 Open Silo Example
               7.3 Shielded Skyshine Sources
               7.4 Computational Resources for Skyshine Analyses
          8: Radiation Streaming Through Ducts
               8.1 Characterization of Incident Radiation
               8.2 Line-of-Sight Component for Straight Ducts
                    8.2.1 Line-of-Sight Component for the Cylindrical Duct
                    8.2.2 Line-of-Sight Component for the Rectangular Duct
               8.3 Wall-Penetration Component for Straight Ducts
               8.4 Single-Scatter Wall-Reflection Component
               8.5 Photons in Two-Legged Rectangular Ducts
               8.6 Neutron Streaming in Straight Ducts
                    Single-Wall Scattering
                         Multiple-Wall Scattering
               8.7 Neutron Streaming in Ducts with Bends
                    8.7.1 Two-Legged Ducts
                         Neutron Streaming in a Two-Legged Cylindrical Duct
                         Neutron Streaming in a Two-Legged Rectangular Duct
                    8.7.2 Neutron Streaming in Ducts with Multiple Bends
               8.8 Empirical and Experimental Results
          9: Shield Design
               9.1 Shielding Design and Optimization
               9.2 Shielding Materials
                    9.2.1 Natural Materials
                    9.2.2 Concrete
                    9.2.3 Metallic Shielding Materials
                    9.2.4 Special Materials for Neutron Shielding
                         Boron for Neutron Attenuation
                         Lithium for Neutron Attenuation
                    9.2.5 Materials for Diagnostic X-Ray Facilities
               9.3 A Review of Software Resources
               9.4 Shielding Standards
          10: Health Physics
               10.1 Deterministic Effects from Large Acute Doses
                    10.1.1 Effects on Individual Cells
                    10.1.2 Deterministic Effects in Organs and Tissues
                    10.1.3 Potentially Lethal Exposure to Low-LET Radiation
               10.2 Hereditary Illness
                    10.2.1 Classification of Genetic Effects
                    10.2.2 Estimates of Hereditary Illness Risks
               10.3 Cancer Risks from Radiation Exposures
                    10.3.1 Estimating Radiogenic Cancer Risks
               10.4 The Dose and Dose-Rate Effectiveness Factor
                    10.4.1 Dose–Response Models for Cancer
                    10.4.2 Average Cancer Risks for Exposed Populations
               10.5 Radiation Protection Standards
                    10.5.1 Risk-Related Dose Limits
                    10.5.2 The 1987: NCRP Exposure Limits
          Acknowledgments
          References
     12: High Performance Computing in Nuclear Engineering
          1: Introduction
          2: Main Computer and Processor Architectures
               2.1 Main Architecture Classes for High Performance Computing
               2.2 SIMD Architectures
               2.3 MIMD Architectures
               2.4 Dataflow and Systolic Architectures: Specialized ArchitecturesVersus Generic Ones
               2.5 Vector Architectures
          3: Parallelism Models
               3.1 Overview
               3.2 Shared Memory Model
               3.3 Threads Model
               3.4 Message Passing Model
               3.5 Data Parallel Model
               3.6 Other Models
                    3.6.1 Hybrid
                    3.6.2 Single Program Multiple Data (SPMD)
                    3.6.3 Multiple Program Multiple Data (MPMD)
               3.7 The Different Levels of Parallelism
                    3.7.1 First Level: Distributed Computing
                    3.7.2 Second Level: Coarse Grain Parallel Computing
                    3.7.3 Third Level: Fine Grain Parallel Computing
          4: Designing Parallel Programs
               4.1 Automatic Versus Manual Parallelization
               4.2 Understand the Problem and the Program
               4.3 Partitioning
                    4.3.1 Domain Decomposition
                    4.3.2 Functional Decomposition
                         EcosystemModeling
                         Signal Processing
                         Climate Modeling
               4.4 Communications
                    4.4.1 Who Needs Communications?
                         You Do Not Need Communications
                         You Do Need Communications
                    4.4.2 Factors to Consider
                         Cost of Communications
                         Latency Versus Bandwidth
                         Visibility of Communications
                         Synchronous Versus Asynchronous Communications
                         Scope of Communications
                         Efficiency of Communications
               4.5 Synchronization
                    4.5.1 Types of Synchronization
                         Barrier
                         Lock/Semaphore
                         Synchronous Communication Operations
               4.6 Data Dependencies
                    4.6.1 Definition
                    4.6.2 Examples
                    4.6.3 How to Handle Data Dependencies
               4.7 Load Balancing
                    4.7.1 How to Achieve Load Balance
                         Equally Partition theWork Each Task Receives
                         Use Dynamic Work Assignment
               4.8 Granularity
                    4.8.1 Computation/Communication Ratio
                    4.8.2 Fine Grain Parallelism
               4.9 Limits and Costs of Parallel Programming
                    4.9.1 Amdahl's Law
                    4.9.2 Complexity
                    4.9.3 Portability
                    4.9.4 Resource Requirements
                    4.9.5 Scalability
          5: Use of HPC for Nuclear Energy Application: Overview
               5.1 The Virtual Power Plant Challenge
                    5.1.1 Description
                    5.1.2 Motivation
                    5.1.3 Main Challenges
               5.2 Other Examples and Use
          6: Illustration of HPC Use on Different Applications
               6.1 HPC for Reactor Core Simulation
                    6.1.1 Introduction
                    6.1.2 Major Challenges
                    6.1.3 HPC in Monte Carlo Simulations
                         Principles for a Parallel Implementation
                         Performances
                         Future Challenges
                    6.1.4 HPC in Deterministic Simulations
                         The Different Level of Parallelism
                         First Level: Multiparameterized Calculations
                         Second Level: Multi-Domain Calculations
                         Third Level: Fine Grain Parallelism Model
               6.2 HPC for CFD and DNS
                    6.2.1 Main Industrial Issues
                    6.2.2 The Multi-Scale Approach
                    6.2.3 HPC for DNS
                    6.2.4 HPC for LES
                    6.2.5 Other Fields
               6.3 High Performance Computing for Materials Science
                    6.3.1 Introduction
                    6.3.2 Theoretical and Computational Methods
                    6.3.3 Models and Simulations of Nuclear Fuels and Structural Materials
                    6.3.4 Fuel Performance Codes
                    6.3.5 Conclusions
          7: Conclusion and Open Issues
          References
Volume III: Reactor Analysis
     13: Analysis of Reactor Fuel Rod Behavior
          1: Introduction
          2: The LWR Fuel Element: A General Outline
               2.1 The Fuel Pellet
               2.2 The Fuel Rod
               2.3 The Fuel Element
          3: Properties of Oxide Nuclear Fuel
               3.1 Structure and Thermal Expansion
               3.2 Thermal Conductivity
                    3.2.1 UO2
                    3.2.2 Mixed Oxides
                    3.2.3 Effects of Irradiation
               3.3 Heat Capacity
               3.4 Melting Temperature
          4: Properties of Cladding Materials for LWRs Fuel
               4.1 Composition
               4.2 Microstructure
               4.3 Thermal Properties
                    4.3.1 Linear Thermal Expansion
                    4.3.2 Thermal Conductivity
                    4.3.3 Specific Heat Capacity
                    4.3.4 Emissivity
               4.4 Mechanical Properties
                    4.4.1 Elastic Constants
                    4.4.2 Plastic Deformation
               4.5 Irradiation Effects
                    4.5.1 Irradiation-Induced Growth
                    4.5.2 Irradiation-Induced Hardening
                    4.5.3 Irradiation-Induced Creep
                    4.5.4 Corrosion and Hydrogen Pickup
               4.6 High-Temperature Effects
                    4.6.1 High-Temperature Corrosion
                    4.6.2 High-Temperature Deformation
          5: Basic Phenomena for In-Reactor Performance
               5.1 Neutronic Aspects of Nuclear Fuel Rods
                    5.1.1 Nuclide Evolution in Nuclear Fuel
                    5.1.2 The Basic Equations
                    5.1.3 Burnable Absorbers
               5.2 Heat Transfer and Thermal Characteristics
                    5.2.1 Axial Heat Transport in the Coolant
                    5.2.2 Heat Transport through the Cladding
                    5.2.3 Heat Transport from the Cladding to the Fuel Pellet
                    5.2.4 Effects of Irradiation on Gap Conductance
                    5.2.5 Heat Transport in the Fuel Pellet
               5.3 Mechanical Behavior
                    5.3.1 Main Assumptions and Equations
                    5.3.2 Calculation of Strains
                         Elastic Strain
                         Nonelastic Strain
                    5.3.3 Boundary Conditions
                         Radial Boundary Conditions
                         Axial Boundary Conditions
               5.4 Fission Gas Behavior
                    5.4.1 Basic Mechanisms
                         Recoil, Knockout and Sputtering
                         Lattice Diffusion of Single Gas Atoms
                         Trapping
                         Irradiation-Induced Resolution
                         Grain Boundary Diffusion
                         Grain Boundary Sweeping or Grain Growth
                         Bubble Migration
                         Bubble Interconnection
                    5.4.2 Modeling the Fission Gas Behavior
                         Intragranular Behavior
                         Intergranular Behavior
                         Coupling Intra and Intergranular Behavior
                         Swelling
          6: Typical Phenomena and Issues in the Design and Licensingof LWR Fuels
               6.1 High Burnup Structure
                    6.1.1 Characteristics of the High Burnup Structure
                    6.1.2 Importance of the High Burnup Structure
                    6.1.3 Modeling of the High Burnup Structure
               6.2 Pellet-Cladding Interaction
                    6.2.1 Pellet-Cladding Mechanical Interaction
                    6.2.2 Irradiation–Induced Stress Corrosion Cracking
                         Sufficient Stress
                         Sufficient Time
                         Susceptible Material
                         Proper Chemical Environment
                         Mitigating PCI
                         Modeling PCI
                    6.2.3 Outside-In Cracking Caused by Power Ramps
               6.3 Pellet-Coolant Interaction
               6.4 Loss-of-Coolant Accidents
                    6.4.1 Sequence of Events during a LOCA
                    6.4.2 Main Characteristics of a LOCA Failure
                    6.4.3 Current LOCA Safety Criteria
                         LOCA Criterion Based on Zero-Ductility
                         LOCA Criterion Based on Integral Quench Tests
                    6.4.4 Extension to High Burnup Fuel
                         Zero-Ductility Limit at High Burnup
                         LOCA High Burnup Limit from Integral Quench Tests
               6.5 Reactivity-Initiated Accidents
                    6.5.1 Sequence of Events during a RIA
                    6.5.2 Main Characteristics of RIA Failures
                    6.5.3 RIA Safety Criteria
          7: Uncertainty Analysis
          8: Outlook
          Acknowledgment
          References
     14: Noise Techniques in Nuclear Systems
          1: Introduction
          2: Zero Power Reactor Noise
               2.1 Methodology of Zero Power Neutron Noise
                    2.1.1 Forward Approach
                    2.1.2 Backward Approach
               2.2 Reactivity Measurements in Traditional Systems with StationaryPoisson Sources
                    2.2.1 The Feynman-Alpha (Variance to Mean) Method
                    2.2.2 The Rossi-Alpha (Correlation) Method
                    2.2.3 The Bennett Variance Method
                    2.2.4 Mogilner's Zero Crossing Method
                    2.2.5 The Cf-252: Method
               2.3 Reactivity Measurements in ADS
                    2.3.1 Spallation Source
                    2.3.2 Pulsed Source in Feynman- and Rossi-Alpha Applications
                    2.3.3 Feynman-Alpha with Deterministic Pulsing
                    2.3.4 Feynman-Alpha with Stochastic Pulsing
                    2.3.5 Rossi-Alpha with Stochastic Pulsing
               2.4 Pulse Counting Techniques in Nuclear MaterialManagement (Safeguards)
                    2.4.1 Neutron Factorial Moments
                    2.4.2 Gamma Photon Factorial Moments
                    2.4.3 Mixed Moments
                    2.4.4 Multiplicity Detection Rates
          3: Power Reactor Noise Theory
               3.1 Basic Principles
               3.2 Space-Time Dependent Reactor Kinetics in Diffusion Theory
                    3.2.1 Static Equations
                         One-GroupTheory
                         Two-GroupTheory
                    3.2.2 Time-Dependent One-Group Diffusion Equations
                    3.2.3 The Flux Factorization and the Kinetic Approximations
                         The Point Reactor Approximation
                         The Adiabatic Approximation
               3.3 Small Space-Time Dependent Fluctuations: Power Reactor Noise
                    3.3.1 Neutron Noise in One-Group Diffusion Theory
                    3.3.2 The Factorization of the Neutron Noise
                         Determination of the Fluctuations of the Amplitude Factor
                         Determination of the Fluctuations of the Shape Function
                         Full Solution in One-Group Diffusion Theory
                    3.3.3 Neutron Noise in Two-Group Diffusion Theory: The Local Component
                         Direct Approach: the Green’s Function Matrix
                         Adjoint Approach: The Dynamic Adjoint Function
          4: Applications of Power Reactor Noise Diagnostics
               4.1 Unfolding Noise Source Parameters with Noise Diagnostics
                    4.1.1 Localization of Absorbers of Variable Strength
                    4.1.2 Localization of Vibrating Control Rods
                    4.1.3 Flow Velocity Estimations
                         Flow Velocity Estimations in BWRs fromthe Neutron Noise
                         Flow velocity Estimations in PWRs from Temperature and Neutron Noise
                    4.1.4 Miscellaneous Other Applications
                         Diagnostics of Core-Barrel Vibrations in PWRs
                         Detection of Impacting Detector Strings in BWRs
          5: Special Noise Techniques: Determination of Core GlobalDynamical Parameters
               5.1 Determination of the Decay Ratio in BWRs
                    5.1.1 Stability Indicator
                    5.1.2 Stability Mechanism of a BWR
                    5.1.3 Types of BWR Instabilities
                    5.1.4 Combined Types of Oscillations
               5.2 Determination of the Moderator Temperature Coefficient ofReactivity in PWRs
                    5.2.1 Definition of the MTC
                    5.2.2 Derivation of the MTC Noise Estimate
                    5.2.3 Measurement by Noise Analysis Technique
                    5.2.4 Elaboration of a Correct MTC Noise Estimator
          6: Conclusions and Open Issues
          Acknowledgments
          References
     15: Deterministic and Probabilistic Safety Analysis
          1: Origin and Methodological Framework of DeterministicSafety Analysis
               1.1 Origin of Nuclear Power Safety and Regulation
                    1.1.1 First Implementation of Nuclear Safety in the USA
                    1.1.2 Reactor Design Safety by Du Pont Engineers
                    1.1.3 US Atomic Energy Commission
                    1.1.4 International Atomic Energy Agency (IAEA)
               1.2 Evolution of Methods for Safety Assurance
               1.3 Defense-in-Depth
               1.4 Design Basis Accidents
               1.5 Single Failure Criterion
               1.6 Accident Types
                    1.6.1 Loss of Coolant Accidents
                    1.6.2 Transient Events
               1.7 General Design Criteria
                    1.7.1 Quality Control Criterion
                    1.7.2 Design Bases for Protection against Natural Phenomena
                    1.7.3 Fire Protection
                    1.7.4 Environmental and Dynamic Effects Design Bases
                    1.7.5 Sharing of SSCs
                    1.7.6 Proven Engineering Practices
                    1.7.7 Quality Assurance
                    1.7.8 Self-Assessment
                    1.7.9 Peer Reviews
                    1.7.10 Human Factors
                    1.7.11 Safety Assessment and Verification
                    1.7.12 Radiation Protection
                    1.7.13 Operating Experience and Safety Research
                    1.7.14 Defense against Severe Accidents
               1.8 Requirements and Standards for Nuclear Safety
                    1.8.1 American National Standard Nuclear Safety Criteria
               1.9 US Regulatory Requirements for Deterministic Safety Analyses
               1.10 Safety Features for Future Nuclear Plants
          2: Evolution of Probabilistic Safety Assessment and Applications
               2.1 Safety Issues in Nuclear and Aerospace Industries
                    2.1.1 Safety Issues in Nuclear Industry
                    2.1.2 Safety Issues in Aerospace Industry
               2.2 Reactor Safety Study (WASH-1400)
                    2.2.1 Motivation – ECCS Issue and Loss of Fluid Tests
                    2.2.2 RSS Staff
                    2.2.3 Fault Trees and Event Trees
                    2.2.4 Initiating Events
                    2.2.5 Failure Data
                    2.2.6 Uncertainty Analysis
                    2.2.7 Sensitivity Analysis
                    2.2.8 Consequence Analysis
                    2.2.9 Release Categories
                    2.2.10 Comparison with Other Risks
                    2.2.11 RSS Results
                    2.2.12 APS Review
               2.3 Post-RSS Review and the Three Mile Island Accident
               2.4 Post-TMI Accident and Revival of the Use of PSA
               2.5 Safety Goals
               2.6 NUREG-1150 Studies
               2.7 IPE and IPEEE
               2.8 NRC'S PRA Policy Statement
               2.9 EPRI's PSA Applications Guide
               2.10 Guidelines for Risk-Informed Regulation
               2.11 Reactor Oversight Process
               2.12 Maintenance Rule
               2.13 Risk-Informed Improvement to Technical Specifications
               2.14 Risk-Informed Licensing Structure for Design Safety
          3: Probabilistic Safety Assessment
               3.1 Strength of PSA
               3.2 Steps in Conducting a Probabilistic Safety Assessment
                    3.2.1 Objectives and Methodology
                    3.2.2 Familiarization and Information Assembly
                    3.2.3 Identification of Initiating Events
                    3.2.4 Sequence or Scenario Development
                    3.2.5 Logic Modeling
                    3.2.6 Failure Data Collection, Analysis and Performance Assessment
                    3.2.7 Quantification and Integration
                    3.2.8 Uncertainty Analysis
                    3.2.9 Sensitivity Analysis
                    3.2.10 Risk Ranking and Importance Analysis
                    3.2.11 Interpretation of Results
               3.3 A Simple Example of PSA
                    Identification of Initiating Events
                         Scenario Development
                         Logic Modeling
                         Failure Data Analysis
                         Quantification
               3.4 Future Outlook of Safety Analysis and Research Needs
          References
     16: Multiphase Flows: Compressible Multi-Hydrodynamics
          1: Introduction and Scope I
          2: Basics of Coarse-Graining
               2.1 The Two-Fluid Model
               2.2 The Kinetic Theory Model
               2.3 The Hybrid (Symmetry-Breaking) Model
          3: A General Formulation
          4: Non-Dissipative Model
               4.1 Rigid Particles
                    4.1.1 Rigid Particles, No Velocity Fluctuations
                    4.1.2 Rigid Particles with Added-Mass Velocity Fluctuations
               4.2 Compressible Particles
          5: Dissipative Model
               5.1 Noncompressible Particles: Solid Grains or Drops
                    5.1.1 The Dissipation Rate
                    5.1.2 The Constitutive Laws
               5.2 Compressible Particles: Bubbles
                    5.2.1 The Dissipation Rate
                    5.2.2 The Constitutive Laws
               5.3 Final Form of the Model*-20pt
          6: Summary of Key Results
               6.1 Hybrid Approach for Dispersed Mixtures
               6.2 Supplementary Equations
                    6.2.1 Pseudo-Turbulent Kinetic Energies
                    6.2.2 Volume Fraction Transport
                    6.2.3 Interfacial Energy Transport
                    6.2.4 Particle Deformation and Dynamics of Interfaces
               6.3 Hyperbolicity
               6.4 Nuclear Reactor (Design) Systems Codes
          Acknowledgments
          A: Rigid Spheres in a Nonviscous Fluid
          B: Hyperbolicity Aspects of the Effective Field Model
          C: Including Surface Tension
          PART II: COMPUTATION WITH EFFECTIVE-FIELD MODELS OFMULTIPHASE FLOWS
          7: Introduction and Scope II
          8: Strategy for Computing Compressible Multi-Hydrodynamics
          9: Basics: The Riemann Problem and the Godunov Method
               9.1 The Riemann Problem
               9.2 The Godunov Method
          10: Approximate Flux ``Splitting'' Schemes for Single Phase Flows
               10.1 Characteristics-Based Flux Splitting
               10.2 Direct Flux Splitting
                    Remarks on Performance
               10.3 Advection Upstream Splitting
                    Remarks on Performance
          11: Advection Upstream Splitting for the Effective Field Model
               11.1 Recasting the System of Equations in Quasi-Conservative Form
               11.2 Numerical Discretization
               11.3 Time Integration
          12: Numerical Testing in the ARMS Code
               12.1 Uniformly Translating Body-and-Fluid System
               12.2 The Faucet Problem
               12.3 Fitt's Problem
               12.4 Shock Tube Problems
               12.5 Particle Cloud Dynamics in Gaseous Shocks
          13: Conclusions and Outlook
          D: Sample Computational Results
          Acknowledgment
          References
          Part I
          Part II
     17: Sensitivity and Uncertainty Analysis, Data Assimilation
          1: Introduction
          2: Measurement Uncertainties
               2.1 Basic Concepts
               2.2 Classification of Measurement Errors
               2.3 Probabilities and Relative Frequencies: Random and Systematic Errors
               2.4 Direct Measurements
               2.5 Indirect Measurements: Propagation of Errors
               2.6 Glossary
          3: Statistical Methods for Sensitivity and Uncertainty Analysis
               3.1 Reliability Algorithms: FORM and SORM
               3.2 Design of Experiments and Screening Design Methods
               3.3 Sampling-Based Methods
               3.4 Variance-Based Methods
          4: Deterministic Computation of Response Sensitivities to ParametersUsing Adjoint Operators
               4.1 Introduction
               4.2 Sensitivity Analysis of Nonlinear and Linear Systems with Feedbackand Operator-Type Responses
                    4.2.1 The Forward Sensitivity Analysis Procedure (FSAP)
                    4.2.2 Adjoint (Local) Sensitivity Analysis Procedure (ASAP)
               4.3 Sensitivity Analysis of Augmented Systems with Feedback
                    4.3.1 The Forward Sensitivity Analysis Procedure (FSAP)
                    4.3.2 The Adjoint Sensitivity Analysis Procedure (ASAP)
               4.4 Illustrative Application of ASAP: Adjoint Sensitivity Analysis ofMarkov Dynamic Reliability Models
               4.5 Global Optimization and Sensitivity Analysis
                    4.5.1 Critical Points and Global Optimization
                    4.5.2 Sensitivity Analysis
                    4.5.3 Global Computation of Fixed Points
          5: Probability Theory and Uncertainty Information
               5.1 Assigning Priors under Incomplete Knowledge: Group Theory andEntropy Maximization
               5.2 Recommending Nominal Values and Uncertainties: Decision Theory
          6: Model Calibration Through Data Assimilation for Best-EstimatePredictions
               6.1 Introduction
               6.2 Mathematical Formalism
               6.3 Data Consistency and Rejection Criteria
               6.4 Illustrative Application to Model Calibration for a BenchmarkBlowdown Experiment
          7: Model Validation and Calibration: Concluding Remarks andOpen Issues
          References
     18: Reactor Physics Experiments on Zero Power Reactors
          1: The Contribution of CEA Critical Mock-Ups in Nuclear ReactorSimulation
          2: Description of the EOLE Mock-Up
          3: Experimental Programs on the EOLE Mock-Up
               3.1 The EPICURE Program
               3.2 The MISTRAL Program
               3.3 The BASALA Program
               3.4 The ADAPh Program
               3.5 The FUBILA Program
               3.6 The FLUOLE Program
                    3.6.1 Reason for the Program
                    3.6.2 Characteristics of the FLUOLE Program
               3.7 The PERLE Program
                    3.7.1 Reason for the Program
                    3.7.2 PERLE Program Characteristics
                         The Homogeneous Configuration
                         Configuration with “EPR Type Reflector”
               3.8 The AMMON Program and the Jules Horowitz Reactor
               3.9 MOX Powder Criticality Requirements
               3.10 Criticality at Loading
               3.11 Plutonium and High Combustion Rate Control. EPR Support
               3.12 Support Program for CELESTIN Reactors
               3.13 An Experimental Platform
               3.14 Support for Generation IV Reactor Concepts
               3.15 Conclusions
          4: Description of the MINERVE Reactor
               4.1 General Description
                    4.1.1 The Cavity
                    4.1.2 Driver Zone Fuel Elements
                    4.1.3 The External Reflector
                    4.1.4 The Central Cavity
                    4.1.5 Control-Command
               4.2 Advantages of the MINERVE Reactor
               4.3 Coupled Assemblies
                    4.3.1 MELODIE Assembly Representative of Pressurized Water Lattices
                         General Description
                         R1-UO2: Lattice Representative of a UO2-PWR Spectrum
                         R1-MOX Lattice Representative of a MOX-PWR Spectrum
                         R2-UO2: Lattice Representative of a Dissolver Spectrum
                         BWR Lattice
                    4.3.2 MORGANE Assembly for Lattices Representative of Under-ModeratedReactors (RSM)
                         General Description
                         MORGANE-R Lattice
                         MORGANE-S Lattice
                    4.3.3 ERMINE Assembly for Fast Neutron Multiplier Lattices
                    4.3.4 ELOISE Assembly for Heavy Water Moderated Lattices
          5: Experimental Programs in the MINERVE Reactor
               5.1 Main Programs Achieved Between 1959: and 1990
               5.2 The CREDIT BURN UP Program (From 1993: to 2001)
               5.3 The CERES Program (From 1992: to 1995)
               5.4 The High Burn-Up (HTC) Program (From 2003: to 2004)
               5.5 The VALMONT Program (2003–2004)
               5.6 The ADAPh Program (2005)
               5.7 The OSMOSE Program
               5.8 The OCEAN Program
               5.9 Training Activities
                    5.9.1 EDF Training
                    5.9.2 INSTN Training
                    5.9.3 Other Training
               5.10 The Gas Fast Reactor (GFR) Program
               5.11 The HTR Program
               5.12 HTC Program Supplement
               5.13 Program on Structure Materials and Moderators
               5.14 FP and Absorber Supplementary Program
               5.15 Program in Support of JHR for Qualification of HORUS3D for U3Si2
               5.16 Cadmium Measurements
               5.17 Other Programs
               5.18 Conclusion
          6: Description of the MASURCA Reactor
               6.1 Core Building Principles
               6.2 Simulation Materials
          7: Experimental Programs in MASURCA
               7.1 The RZ and PLUTO Programs (1969–1975)
               7.2 The PECORE Program (1975)
               7.3 The PRE RACINE and RACINE Programs (1976–1984)
               7.4 The BALZAC Program (1985–1988)
               7.5 The CONRAD Program (1989–1992)
               7.6 The BERENICE Program (1993)
               7.7 The CIRANO Program (1994–1997)
               7.8 The COSMO Program (1998–1999)
               7.9 The MUSE Program (2000–2004)
               7.10 The Facility Refurbishment Project
               7.11 A Program in Support of SFR and the 2020 Prototype: GENESIS
               7.12 A Program in Support of GFR: ENIGMA
               7.13 A ``FBR Large Cores'' Generic Study Program
               7.14 A ``Reflector and Shield'' Program
               7.15 A ``Deteriorated and Accidental Configuration'' Program
          8: Experimental Methods Used and Being Developed on These CriticalMock-Ups
               8.1 The Main Measuring Techniques Used
                    8.1.1 Measurements by Miniature Fission Chambers
                    8.1.2 Measurements by Spectrometry
               8.2 Classification
               8.3 Measurement Electronics at EOLE/MINERVE
                    8.3.1 gamma Spectrometry Benches
                    8.3.2 Automatic Changer
                    8.3.3 Use of DSP
               8.4 Fission Chambers
               8.5 Gamma Ionization Chambers
               8.6 Fissile and Activation Detectors
               8.7 Procedures Linked to the Oscillation Technique
                    8.7.1 Oscillator
                    8.7.2 The Automatic Pilot Rod
                    8.7.3 Acquisition and Online Processing System for Oscillation Measurements
                    8.7.4 Active Sample Handling Equipment
                    8.7.5 Oscillation Samples
                         Sample Origin and Manufacturing
                         Sample Transport and Transfer
          9: Integral Parameter Determination Through Experiment
               9.1 Critical Size
                    9.1.1 Application of Critical Size Determination
               9.2 Reactivity Effect Measurements
                    9.2.1 Reactivity Worth Measurement by Inverse Kinetics
                    9.2.2 Reactivity Effects by Subcritical Measurements
                    9.2.3 Principle of Subcritical Measurements
                    9.2.4 Amplified Source Method (ASM)
                    9.2.5 Modified Source Multiplication (MSM) Method
                    9.2.6 Practical Implementation of ASM and MSM Subcritical Measurements
                    9.2.7 Associated Uncertainties
                    9.2.8 Example: Isothermal Temperature Coefficient (ITC)
                    9.2.9 Reactivity Effect Measurements by Sample Oscillation
                         Principle
                         Practical Implementation
                         Calibration of the Automatic Pilot Rod
                         Signal Calibration
               9.3 Measurement of Fission Rate Distributions
                    9.3.1 Distributions by Fission Chambers
                         RadialMeasurements
                         AxialMeasurements
                    9.3.2 Distributions by Integral Gamma Spectrometry
                         RadialMeasurements
                         AxialMeasurements
                    9.3.3 Particular Use of Fission Rate Distributions: The Buckling Estimation
                    9.3.4 Determination of the Reflector Saving
                    9.3.5 Adjustment of Fission Maps by Particular Peaks
                         Principle of Peak Check Technique
                         Associated Uncertainties
               9.4 Spectral Indexes
                    9.4.1 Basic Principle
                         Some Examples
                    9.4.2 Modified Conversion Factor
               9.5 gamma Heating Measurements
                    9.5.1 Principle
                    9.5.2 gamma Dose Calculation
                    9.5.3 The Different Types of TLDs Used
               9.6 Neutron Noise Measurements
                    9.6.1 The Power Spectral Density (PSD) Method
                    9.6.2 Experimental Principle
          10: Conclusion
          References
               Generalities
               Programmes in EOLE
               Programmes in MINERVE
               Programmes inMASURCA
               Experimental Techniques andMethods
Volume IV: Reactors of Generations III and IV
     19: Pressurized LWRs and HWRs in the Republic of Korea
          1: New Pressurized LWRs Built (or To Be Built)in the Republic of Korea
               1.1 Introduction
               1.2 OPR1000 (Optimized Power Reactor 1000)
                    1.2.1 Design Description
                         Building and Structure
                         Primary System
                         Secondary System
                         Control and Electrical Systems
                    1.2.2 Major Safety Design Features
                         Safety
                         Severe Accident
               1.3 APR1400 (Advanced Power Reactor 1400)
                    1.3.1 Design Description
                         Building and Structure
                         Primary System
                         Secondary System
                         MMIS and Electrical System
                    1.3.2 Major Safety Design Features
                         Safety
                         Severe Accident
                         Proven and Evolutionary Technology
               1.4 Operation and Construction
                    1.4.1 Status of Operation
                    1.4.2 Construction
                         Reactor Containment Building Work
                         Modularization
                         APR1400 Construction Schedule
          2: CANDU Reactors in the Republic of Korea
               2.1 Introduction
               2.2 System Description
                    2.2.1 CANDU Reactor Model
                    2.2.2 Primary Heat Transport System (PHTS)
                    2.2.3 Moderator System
                    2.2.4 Emergency Core Cooling System (ECCS)
                    2.2.5 Shutdown System
                    2.2.6 Containment System
               2.3 Major Safety Design Features
                    2.3.1 Defense in Depth
                         Two Group Concept
                         Redundancy
                         Separation
                         Fail-Safe Feature
                    2.3.2 Availability
               2.4 Status of Operation
               2.5 Spent Fuel Storage Facility
                    2.5.1 Wet Storage of Spent CANDU Fuel
                    2.5.2 Dry Storage of Spent CANDU Fuel
          3: Conclusions
          References
     20: VVER-Type Reactors of Russian Design
          1: Introduction
          2: VVER-440 Reactors
               2.1 Design Description
                    2.1.1 Buildings and Structures
                         Reactor Building
                         Pressure Relief Tower
                         Auxiliary Building
                         Turbine Building
                    2.1.2 Systems of the Primary Circuit
                         Reactor Coolant System
                         Reactor Vessel and Internals
                         Reactor Core
                         Reactor Coolant Pump
                         Pressurizer
                         SteamGenerator
                         Chemical and Volume Control System
                    2.1.3 Systems of the Secondary Circuit
                         Main Steam Line System
                         Main Feedwater System
                         Turbine
                         Generator
                         Moisture Separator–Reheater
                    2.1.4 Instrumentation and Electrical Systems
                         Instrumentation and Control Systems
                         Main Control Room
                         Electrical Systems
               2.2 Basic Safety Properties
                    2.2.1 Safety Philosophy
                    2.2.2 Safety Systems and Properties
                    2.2.3 Maximum Design Basis Accident
                    2.2.4 Severe Accidents
                    2.2.5 Seismic Design
               2.3 Operational Experience and Decommissioning
                    2.3.1 Operational Experience
                    2.3.2 Life-Time Extension
          3: VVER-1000 Reactors
               3.1 Design Description
                    3.1.1 Buildings and Structures
                         Reactor Building
                         Auxiliary Building
                         Turbine Building
                    3.1.2 Systems of Primary Circuit
                         Reactor Coolant System
                         Reactor Vessel and Internals
                         Reactor Coolant Pump
                         Pressurizer
                         SteamGenerator
                         Chemical and Volume Control System
                    3.1.3 Secondary-Side Systems
                         Main Steam Line System
                         Main Feedwater System
                         Turbine
                         Generator
                    3.1.4 I&C and Electrical Systems
                         I&C System
                         Main Control Room
                         Electrical Systems
               3.2 Main Aspects of VVER-1000 Safety
                    3.2.1 Safety Philosophy
                    3.2.2 Safety Systems and Distinctive Features
                         Protective Systems
                         Localizing Systems
                         Supporting Systems
                         Control Systems
                    3.2.3 Maximum Design Basis Accident
                    3.2.4 Severe Accidents
                    3.2.5 Seismic Design
               3.3 Operational Experience
          4: Conclusion
     21: Sodium Fast Reactor Design
          1: Motivations for Fast Neutron Systems
               1.1 Basic Principles and Consequences
                    1.1.1 Conditions for Breeding
                    1.1.2 Simplified Neutronic Balance in a PWR
                    1.1.3 Simplified Neutronic Balance in a FBR
                    1.1.4 Balances Comparison
               1.2 Effective Utilization of Resources
                    1.2.1 Uranium Resources and Breeding
               1.3 Flexible Use of Actinides
               1.4 Waste Minimization*6pt
          2: SFR History and Current Projects
               2.1 Overview
               2.2 USA
               2.3 Russia
               2.4 Europe
                    2.4.1 France
                    2.4.2 UK
                    2.4.3 Germany
                    2.4.4 Italy
                    2.4.5 Belgium, Netherland
                    2.4.6 Multinational Project: EFR
               2.5 Japan
                    2.5.1 Joyo
                    2.5.2 Monju
                    2.5.3 Rapid-L
                    2.5.4 L-4S "Nuclear Battery''
                    2.5.5 Commercial Fast Reactor Development Program
               2.6 India
                    2.6.1 FBTR
                    2.6.2 PFBR
               2.7 China
               2.8 Korea
          3: Basic Design Choices
               3.1 Sodium as Coolant
                    3.1.1 Physical Properties
                    3.1.2 Chemical Properties
                    3.1.3 Neutronic Properties
               3.2 Fuel Design
                    3.2.1 Fuel Element
                    3.2.2 Fuel Subassembly
               3.3 Pool/Loop and Modular Design
                    3.3.1 Features of the Primary Circuit Concepts
                    3.3.2 Pool Concept: Motivation and Challenges
                    3.3.3 Loop Concept: Motivation and Challenges
                    3.3.4 Modular Concept: Motivation and Challenges
               3.4 Main Components and Systems
                    3.4.1 Description of Heat Transport Circuits and Components
                    3.4.2 Primary Component Layout on the Top Shield
                    3.4.3 Reactor Assembly Support Options
                    3.4.4 Basic Design Options of Primary Circuit Components
                    3.4.5 Design Improvements for Future SFRs
                    3.4.6 Intermediate Circuits and Steam Generator
                    3.4.7 Summary
               3.5 Fuel Handling
                    3.5.1 Function
                    3.5.2 Classification
                    3.5.3 On-Line Verus Off-Line Refuelling
                    3.5.4 Fresh Subassembly Handling
                    3.5.5 Spent Subassembly Handling
                    3.5.6 In-Vessel/Ex-Vessel Storage to Reduce Decay Heat of Subassembly
                         In-Vessel Handling
                         Ex-Vessel Handling
                    3.5.7 Design Validation
                    3.5.8 Innovative Fuel Handling Concepts
               3.6 Recent Evolution
                    3.6.1 Intermediate Coupling Fluid
                         Fluid Preselection
                         Evaluation Method
                         Results
                         Key features for the Pb-Bi alloy
                         Impact on Design
                         Conclusions
                    3.6.2 Advanced Energy Conversion System
                         Introduction
                         Design Consideration for Brayton Cycle
                         Classical Indirect Gas ECS
                         Indirect/Combined ECS
                         Supercritical Carbon Dioxide Indirect ECS
                         Synthesis and Future Prospects of Advanced ECS
                         Nomenclature
                    3.6.3 Plant Layout
                         Reactor Building
                         Crane Hall
                         Above Roof Area
                         Reactor Service Area
                         Fuel and Component Handling Area
                         Steam Generator and DHR Buildings
                         Plant Layout
          4: Safety Principles
               4.1 Introduction
               4.2 Safety Features Associated with Sodium
                    4.2.1 Physical Properties
                    4.2.2 Nuclear Properties
                    4.2.3 Chemical Reactions
                    4.2.4 Thermalhydraulics and Structural Mechanics Considerations
               4.3 Safety Objectives and Principles Applicable for Future Reactors
               4.4 The Defense in Depth Principle
                    4.4.1 The Levels of the Defense in Depth
                    4.4.2 Objectives and Scope of Defense in Depth
               4.5 Safety Approach for the SFR to Address the Severe Plant Conditions
               4.6 SFR: Safety Demonstration vis-à-vis of the Whole Core Melting
                    4.6.1 Prevention of Whole Core Melting Situations
                    4.6.2 Whole Core Melt Situations: Consequences' Control and Mitigation
                         Implementation of Provisions Allowing Mastering the Consequences of the Whole Core Accident
                         Main Phenomena Which Can Lead the Release ofMechanical Energy
                         Radiological Consequences
                    4.6.3 Initiating Events, Sequences, and Situations ``Practically Eliminated''
                    4.6.4 Control and Management of the Safety Functions
                         Reactivity Control
                         Decay Heat Removal
                         Confinement of Radioactive and HarmfulMaterials
                    4.6.5 Other Specific Risks
                         Sodium Fires
                    4.6.6 Hazards
               4.7 R&D Organization
               4.8 Conclusions
          5: The Materials
               5.1 Fuel Materials
                    5.1.1 Oxide
                         Fuel Element Characteristics
                         Irradiation Conditions in Nominal Operation
                         Temperatures in the Fuel Element
                         Beginning of Life Phenomena
                         Phenomena Occurring During the Life in Reactor
                    5.1.2 Metal
                    5.1.3 Properties of Metal Fuel for Design
                         Phase Diagram
                         Thermal Conductivity of Fuel
                         Thermal Conductivity of Fuel with Burnup
                         Coefficient of Thermal Expansion of Fuel
                         Fission Gas Release
                         Hardness ofMaterial – U-15Wt% Pu-6.8Wt%Zr
                         Behavior under Irradiation
                    5.1.4 Carbide and Nitride
                         Properties of Dense Ceramic Fuels
                         Design of Dense Ceramic Fuel Pins
                         Conclusion
               5.2 Structural Materials
               5.3 Absorber Materials
                    5.3.1 Introduction
                    Russia
                    France
                    Japan
                    Main Control Rods Characteristics
                    5.3.2 Boron Carbide
                         Properties
                         Behavior under Neutron Irradiation
                    5.3.3 Absorber Pins
                    5.3.4 Developments
               5.4 Shield Materials
                    5.4.1 Vessel Shielding
                    5.4.2 Sodium Activation
          6: Core Design
               6.1 Performances Objectives and Design Criteria
                    6.1.1 Safety Objectives
                    6.1.2 Flexibility SFR Cores
                    6.1.3 Core Competitiveness
                    6.1.4 Design Criteria
                         Criteria for Fuel Design
                         Criterion of NoMechanical Fuel–Clad Interaction
                         Criterion of Strength for Fuel Rod Due to Internal Pressure
                         Other Design Criteria
                         Criteria forWrapper Tube
                    6.1.5 Core Shape Design
               6.2 Core Neutronics
                    6.2.1 Elementary Physical Analysis
                    6.2.2 Predesign Studies
                    6.2.3 Detailed Design Studies
                    6.2.4 Calculation Tool for Neutronic Core Design
               6.3 Core Thermalhydraulics
                    6.3.1 Core Flow Distribution
                         Objective
                         Method
                         Mixing Coefficients
                    6.3.2 Calculation of Fuel Assembly Thermalhydraulics
                         Introduction
                         Thermal Balance Equation
                         Bundle Flow Distribution
                         Modeling Flow Deviated between Sub-Channels
                    6.3.3 Assessment of Hexcan Temperatures
                         Simplified Description of the Core Thermalhydraulics
                         Calculation of Hexcan Temperatures
                         TRIO-VF Thermalhydraulic Computer Code
                         Core Modeling
               6.4 Core Mechanics
                    6.4.1 Subassemblies Distortions
                    6.4.2 Operating Considerations
                         Safety Considerations
                    6.4.3 Modeling of the SFR Core Static Mechanical Behavior
                    6.4.4 Experimental Validation
                    6.4.5 Conclusion
               6.5 Reactivity Effects
                    6.5.1 Description of the Feedback Effects
                         Doppler Effect
                         Sodium Expansion
                         Clad Expansion
                         Wrapper Expansion
                         Fuel Expansion
                         Grid Expansion
                         Differential Expansion between Core, Vessel and Control Rods
                         Pad Effect
                    6.5.2 Calculation Method
                         Main Principle
                         Cross Section Calculation Method
                    6.5.3 Return to a Temperature Variation
                    6.5.4 Validity of These Coefficients
          7: Specific Thermalhydraulics Issues
               7.1 Thermal Stratification
                    7.1.1 Phenomena
                    7.1.2 Locations Prone to Stratification
                    7.1.3 Effect of Stratification
                    7.1.4 Numerical Simulation of Stratification
                    7.1.5 Experimental Simulation of Stratification
                    7.1.6 Design Guidelines for Stratification
               7.2 Thermal Striping
                    7.2.1 Phenomenon of Striping
                    7.2.2 Locations Prone to Thermal Striping
                    7.2.3 Effect of Striping
                    7.2.4 Prediction of Thermal Striping
                    7.2.5 Design Guidelines for Striping
               7.3 Free Level Fluctuations
                    7.3.1 Phenomenon
                    7.3.2 Locations of Concern
                    7.3.3 Methods for Prediction of Level Fluctuations
               7.4 Cellular Convection
                    7.4.1 Phenomenon
                    7.4.2 Location of Cellular Convection
                    7.4.3 Effects of Cellular Convection
                    7.4.4 Methods for Prediction of Cellular Convection
                    7.4.5 Managing Cellular Convection
               7.5 Gas Entrainment
                    7.5.1 Phenomenon
                         Entrainment Due to Differential Dissolution of Argon
                         Liquid Fall
                         Vortex Activated Entrainment
                         Drain-Type Vortex
                         Shearing of Gas–Liquid Interface
                    7.5.2 Potential Areas for Gas Entrainment
                    7.5.3 Effect of Gas Entrainment
                    7.5.4 Prediction of Gas Entrainment
                    7.5.5 Design Provisions Against Gas Entrainment and Other Remarks
               7.6 Thermalhydraulic Design Criteria and Analysis Methods
                    7.6.1 Temperature Asymmetry in Cold Pool
                    7.6.2 Free Level Fluctuation
                    7.6.3 Free Surface Velocity in the Pool
                    7.6.4 High-Cycle Temperature Fluctuation
                    7.6.5 Heat Loss to Top Shield
                    7.6.6 Analysis Methods*6pt
          8: Specific Structural Mechanics Issues
               8.1 Introduction
               8.2 High Cycle Thermal Fatigue: Thermal Striping and StratificationInstabilities
                    8.2.1 Experimental Evidence of Thermal Striping
                    8.2.2 Assessment of Potential Damage by Thermal Striping at theDesign Stage
                    8.2.3 Conclusion, Future Prospects
               8.3 Free Level, Stratification Level Fluctuations
                    8.3.1 The Free Level Issues
                    8.3.2 In Sodium Stratification Issues
                    8.3.3 Conclusion
               8.4 Seismic-Induced Forces and Their Effects
                    8.4.1 Geologic Phenomena
                    8.4.2 Seismic Risk
                    8.4.3 Site Effects of Seismic Forces
                    8.4.4 Effects of Seismic Forces on Structures
                    8.4.5 Seismic Piping Behavior and Design Criteria
               8.5 Fluid Structure Interaction in the Fast Reactor Cores
                    8.5.1 Short Description of the Structures of the Reactor
                    8.5.2 Methods to Take into Account FSI
                    8.5.3 Seismic Behavior of the Fast Reactor Cores
                    8.5.4 Design Model for the Seismic Behavior of the Core
                    8.5.5 Overflow Instabilities
                    8.5.6 New Fluid Structure Interaction Phenomena to be Investigated
               8.6 Buckling of Thin Shells
                    8.6.1 Buckling Design Approach
                    8.6.2 Simplified Analysis Method for Buckling of Shells Under SeismicLoadings
                    8.6.3 Thermal Buckling Due to Stationary Temperature Gradient
                    8.6.4 Progressive Buckling Due to Moving Temperature Gradients
                    8.6.5 Creep Buckling
                    8.6.6 An Integrated Buckling Analysis of Thin Vessels of Reactor Assembly
                    8.6.7 Investigation of Buckling of Safety Vessel Subjected to Seismic Loading
                    8.6.8 Investigation of Buckling of Top Shield Plates under CDA Loading
                    8.6.9 Experimental Validations of Computer Codes
                         Validation of CAST3M
                         Validation of ABAQUS Code
                    8.6.10 Summary
               8.7 Design Criteria and Analysis Method
                    8.7.1 Loadings
                         Level A Service Loadings
                         Level B Service Loadings
                         Level C Service Loadings
                         Level D Service Loadings
                    8.7.2 Design Limits
                         Strain Limits
                         Creep Damage
                         Fatigue Damage
                         Creep–Fatigue Interaction
                    8.7.3 Analysis Methods
                         Simplified Methods
                         Inelastic Analysis
                    8.7.4 Buckling Design
                         Time Independent Buckling
                         Time-Dependent Buckling Design
          9: Plant Dynamics
               9.1 About the Design Basis Conditions, the Design Extension Conditionsand the Residual Risk
               9.2 Safety Criteria
               9.3 Analysis Methods
                    9.3.1 Rules for the Different Conditions
                         Aggravating failure
                         Examples of combination of IEs
                         Earthquakes
                         Single Failure Criterion
                    9.3.2 Line of Protection Analysis
                    9.3.3 Method for Safety Classification of Reactor Components
                    9.3.4 Probabilistic Safety Assessment
               9.4 Illustration of SFRs Behavior in Typical Transient Situations
               9.5 Anticipated Transients Without SCRAM
          10: Severe Accidents
               10.1 Introduction
               10.2 History
                    10.2.1 Instances of Severe Accidents in Fast Reactors
               10.3 Defense in Depth
                    Level-1
                    Level-2
                    Level-3
                    Level-4
                    Level-5
                    10.3.1 Physical Barriers
               10.4 CDA: Phenomenology
                    10.4.1 Different Phases of a CDA
                         Pre-disassembly Phase
                         Transition Phase
                         Disassembly Phase
                         Mechanical and Thermal Consequences of CDA
               10.5 Analysis for Mechanical Consequences
                    10.5.1 Idealization of Molten Core Expansion Behavior
                    10.5.2 Analysis for Vessel and Roof Mechanical Loading
                         Theoretical Predictions
                         Experimental Validation of Computer Codes: Typical Case Study
                         Structural Integrity Assessment under CDA: Two Case Studies
               10.6 Post Accident Phase
                    10.6.1 Scenarios
                    10.6.2 Core Debris Accommodation
                    10.6.3 In-Vessel Debris Accommodation
                    10.6.4 Ex-Vessel Debris Accommodation
               10.7 Computer Codes and Validation
                    10.7.1 Validation of Codes: A Case Study
               10.8 Innovations Toward Enhanced Safety
                    10.8.1 Core
                    10.8.2 Sodium Fire and Sodium–Water Reactions
                    10.8.3 Reliable and Diverse Shutdown Systems
                    10.8.4 Decay Heat Removal Systems
                    10.8.5 Core Catcher
                    10.8.6 Breakthroughs for Future SFR
               10.9 Summary
          11: French Licensing Experience on SFR
               11.1 Phenix
               11.2 SPX-1
               11.3 SPX-2
          12: Innovative Design Evolutions
               12.1 In India
                    12.1.1 Pool Type Concept
                    12.1.2 Reactor Power
                    12.1.3 Core
                         Fuel
                         Core Layout
                         Core Height
                         Pin and Subassembly Sizes
                    12.1.4 Shutdown Systems
                    12.1.5 Main Heat Transport System
                    12.1.6 DHR System
                    12.1.7 Main Structural Materials
                    12.1.8 Operating Temperatures
                    12.1.9 Reactor Assembly
                    12.1.10 Component Handling
                    12.1.11 Plant Layout
               12.2 In France
                    12.2.1 A Core with Improved Safety Performances
                    12.2.2 A Better Resistance to Severe Accidents and External Hazards
                    12.2.3 An Optimized Energy Conversion System Optimized to Reduceor Exclude the Risk of Sodium–Water Reaction
                    12.2.4 A Reexamination of the Reactor and Its Components Design
                    12.2.5 ASTRID Program
          References
     22: Gas-Cooled Reactors
          1: Gas Cooling
          2: Natural Uranium Fueled Reactors: Magnox and NUGG
               2.1 The Magnox Family
               2.2 Natural Uranium Graphite Gas (NUGG) Reactors
               2.3 Safety of NUGG and MAGNOX Reactors
          3: Advanced Gas-Cooled Reactor (AGR)
          4: High Temperature Reactors HTR
               4.1 Particles, Pebbles and Prisms
               4.2 HTR Demos: Dragon, AVR, Peach Bottom
                    4.2.1 Dragon
                    4.2.2 AVR
                    4.2.3 Peach Bottom
               4.3 Fort St Vrain and THTR Prototypes
                    4.3.1 Fort St Vrain
                    4.3.2 The Schmehausen HTTR
               4.4 Lessons Learned from the First HTR Units
               4.5 Recent Japanese and Chinese Demos
               4.6 GT-MHR and PBMR
                    4.6.1 GT-MHR, Gas Turbine Modular High Temperature Reactor
                    4.6.2 ESKOM PBMR Pebble Bed Modular Reactor
                    4.6.3 PBMR Fuel Fabrication and Fuel Cycle
          5: The NERVA Story (Simpson JW 1995)
          6: Gas Cooling in Generation IV (DEN 2006)
               6.1 VHTR
                    6.1.1 Electricity Production
                    6.1.2 Hydrogen Production
                    6.1.3 Water Desalination
                    6.1.4 NGNP Project (USA)
               6.2 GFR
                    6.2.1 Specific Problems Associated with the GFR
                    6.2.2 The Advantages of the GFR System Have Two Main Origins
          7: Conclusion
          References
     23: Lead-Cooled Fast Reactor (LFR) Design
          1: Lead-Cooled Fast Reactor (LFR) Development
               1.1 Lead–Bismuth Eutectic (LBE) for Submarine Propulsion
               1.2 The Russian Design for Civilian Fast Reactors Cooled by HLM
                    1.2.1 The BREST 300
                    1.2.2 The SVBR-75
               1.3 HLM-Cooled ADS Systems
               1.4 The LFR in Generation IV
               1.5 The LFR and ADS Designs Considered in the Handbook
                    1.5.1 SSTAR
                    1.5.2 ELSY
                    1.5.3 MYRRHA
                    1.5.4 EFIT
          2: Design Criteria and General Specifications
               2.1 Sustainability
                    2.1.1 Resource Utilization
                    2.1.2 Waste Minimization and Management
               2.2 Economics
                    2.2.1 Risk to Capital
                    2.2.2 Other Use of Nuclear Heat
               2.3 Safety and Reliability
                    2.3.1 Operation Will Excel in Safety and Reliability
                    2.3.2 Low Likelihood and Degree of Core Damage
                    2.3.3 Reduced Need for Offsite Emergency Response
               2.4 Proliferation Resistance and Physical Protection
                    2.4.1 Unattractive Route for Diversion of Weapon-Usable Material
                    2.4.2 Increased Physical Protection Against Acts of Terrorism
          3: Neutronics
               3.1 Neutronic Properties of Lead
                    3.1.1 Moderation
                    3.1.2 Absorption
               3.2 Fuel Performances in LFRs
                    3.2.1 Fission Cross Sections
                    3.2.2 Average Number of Fission Neutrons
                    3.2.3 Fuel Utilization
                    3.2.4 Spectrum Evolution with Burn-Up
                    3.2.5 Effective Delayed Neutron Fraction and Prompt Neutrons Lifetime
                    3.2.6 LFR Capabilities of MAs Transmutation
               3.3 Neutronic Performances of Typical Absorbers in an LFR
                    3.3.1 Boron Carbide
                    3.3.2 Indium–Cadmium Eutectic
                    3.3.3 Europium
          4: Lead Properties
               4.1 Physical Properties
                    Normal Melting Point
                         Volume Change at Melting
                         Latent Heat of Melting at the Normal Melting Point
                         Normal Boiling Point
                         Heat of Vaporization at the Normal Boiling Point
                         Saturation Vapor Pressure
                         Surface Tension
                         Density
                         Thermal Expansion
                         Sound Velocity and Compressibility
                         Heat Capacity
                         Critical Constants
                         Viscosity
                         Electric Resistivity
                         Thermal Conductivity and Thermal Diffusivity
               4.2 Chemistry Control and Monitoring Systems
                    4.2.1 The Thermodynamical Base
                    4.2.2 Thermodynamical Data and Diagrams
                         Change in the Standard Free Energy
               4.3 Thermal Hydraulics
          5: Compatibility of Structural Materials with Lead
               5.1 Structural Materials Corrosion in Lead
               5.2 Effect of Lead on Properties of Structural Materials
          6: Core
               6.1 Introductory Remarks for LFR Core Design
                    6.1.1 Preliminary Evaluation of Lead and LBE Impact on Core Design
                    6.1.2 Technological Constraints for LFR Design
               6.2 Conceptual Design Approach
                    6.2.1 Critical Reactors
                    6.2.2 Subcritical Reactors
                         Case Study: EFIT
                    6.2.3 Adiabatic Reactors
               6.3 Design Diagnostics and Post-Process Feedbacks
                    6.3.1 Overall BU Performances
                    6.3.2 Sizing and Placement of Control Systems
               6.4 Reactivity Coefficients
                    6.4.1 Lead Void Reactivity
                    6.4.2 Doppler Effect
                    6.4.3 Dimension and Density Reactivity Coefficients
                    6.4.4 Feedback Reactivity Coefficients
          7: Reactor System
               7.1 Reactor Vessel and Safety Vessel
               7.2 Reactor Internal Structures
               7.3 Steam Generator
               7.4 Primary Coolant Circulation
          8: Decay Heat Removal System
               8.1 Reactor Vessel Air Cooling System
               8.2 Water Loops and Associated Dip Coolers
               8.3 Steam Condensers on the Steam Loops
          9: Nuclear Island
          10: Concluding Remarks and Open Issues
          Acknowledgment
          Abbreviations
          References
     24: GEMast STAR: The Alternative Reactor Technology
          1: Introduction
          2: Supplemental Neutrons from Accelerators
          3: Molten Salt Technology
          4: Graphite Developments
          5: Integrating Accelerators, Molten Salt, and Graphite
          6: Calculations of GEMSTAR Burn-Up Performance
          7: Corrections for MCNP5: Graphite Absorption
          8: GEMast STAR Reactor Parameters
          9: Burning LWR Spent Fuel
          10: Other Fuels
               10.1 Thorium and Depleted Uranium Fuels
               10.2 Fueling GEMSTAR Over the Long Term
          11: Other Factors Affecting GEMSTAR Success
               11.1 Ultimate Ocean Disposal?
               11.2 GEMast STAR Comparison with Fast Breeder Reactors
               11.3 Fusion Neutron Sources
          12: Nonproliferation Advantages of GEMSTAR
          13: Cost Estimation
               13.1 GEMast STAR Accelerator Costs
               13.2 GEMast STAR Reactor Costs and Breakeven Electricity Price
          14: Summary
          References
Volume V: Fuel Cycles, Decommissioning,Waste Disposal and Safeguards
     25: Front End of the Fuel Cycle
          1: Description
          2: Uranium Exploration and Mining
               2.1 The Element Uranium
                    2.1.1 Uranium Resources
                    2.1.2 The Oklo Phenomenon
                         Oklo uranium was indeed different from natural uranium everywhere else. Why?
               2.2 Uranium Exploration
               2.3 Uranium Mining and Milling
               2.4 Sites Rehabilitation
          3: Conversion
          4: Uranium Enrichment
               4.1 Principle, Cascade, SWU, HEU, LEU
               4.2 Enrichment Technologies
                    4.2.1 Gaseous Diffusion
                    4.2.2 Ultracentrifugation
                    4.2.3 Other Methods
          5: Fuel Fabrication
               5.1 Elements of Fuel Design
                    5.1.1 Fissile/Fertile Couple
                    5.1.2 Fuel Material
                    5.1.3 Cladding Materials
                    5.1.4 Absorber Materials
               5.2 The LWR Fuel
                    5.2.1 Fuel Pellets Production
                    5.2.2 Fuel Rods Fabrication
                    5.2.3 Assembly
               5.3 MOX Fuel
               5.4 Other Fuel
                    5.4.1 CANDU
                    5.4.2 FBR
                    5.4.3 HTR
               5.5 In-Reactor PWR Fuel Behavior
          6: Thorium
          7: Plutonium
          References
     26: Transuranium Elements in the Nuclear Fuel Cycle
          1: General Introduction
          2: Fundamental Aspects of Transuranium Fuels
               2.1 General
               2.2 Characteristics of Transuranium Fuel Forms
               2.3 Properties of Transuranium Elements and Compounds
          3: Transuranium Element Fuel and Target Fabrication
               3.1 General Aspects
               3.2 Solid Solution Oxide Fuels Fabrication by Wet Routes (Precipitation,Sol–Gel, and Infiltration)
               3.3 Powder Metallurgy for the Production of Solid Solution Fuels
               3.4 Oxide Fuels with Composite Microstructure
               3.5 Minor Actinide Carbide, Nitride, and Metal Fuels
                    3.5.1 General Considerations
                    3.5.2 Production of Minor Actinide Nitrides
                    3.5.3 Production of Minor Actinide Bearing Metal Fuels
          4: Irradiation Behavior of Transuranium Fuels
               4.1 Mixed Oxide Fuels
               4.2 Metal Fuels
               4.3 Carbide and Nitride Fuels
               4.4 Molten Salt Fuels
               4.5 Other Fuel Types
               4.6 Summary
          5: Reprocessing
               5.1 Introduction
               5.2 Advanced Aqueous Reprocessing
                    5.2.1 Fundamental Studies
                    5.2.2 Process Development
               5.3 Pyro-Reprocessing
                    5.3.1 US Pyrochemistry Projects
                    5.3.2 European Pyrochemistry Projects
                    5.3.3 Liquid–Liquid Reductive Extraction in Molten Fluoride/Liquid Aluminum
                    5.3.4 Technical Uncertainties of the Pyro-Reprocessing
                    5.3.5 Head-End Conversion Processes
          6: Impact of Transuranium Elements on Storage and WasteDisposal Concepts
               6.1 General Aspects
               6.2 Transuranium Elements and Wasteforms
                    6.2.1 Transuranium Elements in Spent Fuel
                    6.2.2 Transuranium Elements in Waste Glass
                    6.2.3 Transuranium Elements in Advanced Cycle Waste Forms
               6.3 Special Wasteforms for the Immobilization of Transuranium Elements
               6.4 Long-Term Behavior of Waste Containing Transuranium Elements
                    6.4.1 Consequences of Alpha-Decay Damage and HeliumBuild-Up in the Waste Form
                    6.4.2 Corrosion Behavior of the Waste Form in Contact with Water
          References
     27: Decommissioning of Nuclear Plants
          1: Nuclear Plants Decommissioning Overview
               1.1 Definition and Scope of Decommissioning
               1.2 Introduction to Some Decommissioning Challenges
                    1.2.1 Organization and Management
                    1.2.2 Safety-Related Issues
                    1.2.3 Decommissioning Funding
                    1.2.4 Waste Management
               1.3 Decommissioning Strategies
                    1.3.1 Overview
                    1.3.2 Issues Affecting the Choice of Decommissioning Strategy
                         National Nuclear Strategies
                         Plant Characteristics
                         Protection of Health, Safety, and the Environment
                         Radioactive Waste Management
                         Future Use of the Site
                         Development of Decommissioning Technologies
                         Cost and Availability of Funds
                         Social and Other Considerations
               1.4 Decommissioning in the World
          2: Decommissioning Organization and Management
               2.1 Overview
               2.2 Issues Affecting Decommissioning Organization and Management
                    2.2.1 Decommissioning Strategy
                    2.2.2 Safety Issues
                    2.2.3 Work Approaches
                    2.2.4 Impact on Staffing
               2.3 Organization and Management in the Various Phases ofDecommissioning
                    2.3.1 The Planning Phase
                    2.3.2 The Transition Phase
                    2.3.3 The Active Phases of Decommissioning
                    2.3.4 The Safe Enclosure Phase
                    2.3.5 The Post-Dismantling Period
                    2.3.6 Spent Fuel and Waste Storage
               2.4 Management for Active Phases of Decommissioning
                    2.4.1 Overview
                    2.4.2 The Decommissioning Management Team
                    2.4.3 Change Management
               2.5 Decommissioning Planning and Licensing
                    2.5.1 Overview
                    2.5.2 Decommissioning Planning
                    2.5.3 Stages of Planning
                    2.5.4 Content of Decommissioning Plan
                    2.5.5 Decommissioning Optimization
                    2.5.6 Project Risk Management
                    2.5.7 Regulatory Approval
                    2.5.8 Work Packages and Procedure
               2.6 Role of Quality Assurance
                    2.6.1 Overview
                    2.6.2 Control of Modifications to the Plant
                    2.6.3 Radiation Protection and Environmental Safety Control
                    2.6.4 Control of Outside Contracted Services
                    2.6.5 Surveillance and Inspections
                    2.6.6 Information Management
                    2.6.7 Safety Audits
                    2.6.8 Management, Assessment and Reporting of Incidents and Events
               2.7 Responsibilities and Qualifications
                    2.7.1 Licensee
                    2.7.2 Decommissioning Project Manager (DPM)
                    2.7.3 Technical Support
                         Radiation Protection
                         Industrial Safety
                         Quality Assurance
                         Engineering
                         Regulatory Control
                    2.7.4 Decommissioning Operations
                         Decontamination and Dismantling
                         WasteManagement
                         Maintenance
                         Specialist Contractors
                    2.7.5 Administration Services
                         Accounting and Finance
                         Contracts and Procurement
                         Information Management
                         Personnel and Training
                    2.7.6 Interfaces
          3: Plant and Site Characterization
               3.1 Initial Plant Characterization
                    3.1.1 Radioactivity Sources
                         Nuclear Reactors
                         Other Nuclear Facilities
                    3.1.2 The Concept and Extent of Characterization
                    3.1.3 Structure Characterization
                    3.1.4 System and Equipment Characterization
               3.2 Site Characterization
                    3.2.1 Surface Soil Contamination
                    3.2.2 The NRC Acceptance Criteria
                    3.2.3 Subsurface Soil Contamination
                    3.2.4 Surface Water Contamination
                    3.2.5 Groundwater Contamination
          4: Decontamination Techniques
               4.1 Overview
                    4.1.1 Objectives of Decontamination Techniques
                    4.1.2 Selection of Decontamination Technologies
                    4.1.3 Survey of Applied Decontamination Techniques
               4.2 Decontamination of Segmented Components
                    4.2.1 Overview
                    4.2.2 Chemical Decontamination
                         Chemical Reagents
                         Spent Decontamination Solutions
                         Guidelines
                    4.2.3 Electrochemical Decontamination
                         Chemical Reagents
                         Secondary-Waste Generation
                         Guidelines
                    4.2.4 Mechanical Decontamination
                         Abrasive-Blasting Decontamination Systems
                         Abrasive Media Used
                         SecondaryWaste Generation
                         Guidelines
                    4.2.5 Decontamination by Melting
                         Current Melting Practices
                         Advantages ofMelting as a Decontamination Technique
                    4.2.6 Other Decontamination Techniques
               4.3 Decontamination of Building Surfaces
                    4.3.1 Overview
                    4.3.2 Basic Techniques
                    4.3.3 Scarifying
                         Needle Scaling
                         Scabbling
                         Concrete Shaving
                         Hydraulic/Pneumatic Hammering
                         Dust Collection
                         Production Rates
                    4.3.4 Guidelines
               4.4 Chemical Decontamination Techniques
                    4.4.1 Overview
                    4.4.2 Water/Steam
                    4.4.3 Strong Mineral Acids
                         Hydrochloric Acid
                         Nitric Acid
                         Sulfuric Acid
                         Phosphoric Acid
                    4.4.4 Acid Solutions
                    4.4.5 Organic/Weak Acids
                         Oxalic Acid
                         Oxalate Peroxide
                         Citric Acid
                         Sulfamic Acid
                    4.4.6 Alkaline Solutions
                    4.4.7 Complexing Agents
                    4.4.8 Oxidizing and Reducing (REDOX) Agents
                         Alkaline Permanganate
                         Low Oxidation-StateMetal Ion (LOMI)
                         Electrochemical Low Oxidation-StateMetal Ion Exchange (ELOMIX)
                         DECOHA Process
                         Chemical Oxidation Reduction Decontamination (CORD)
                         Pressurized Water Reactor Oxidative Decontamination (POD)
                         Bleaching
                         Detergents and Surfactants
                    4.4.9 Organic Solvents
                    4.4.10 Multiphase Treatment Processes
                         Alkaline Permanganate Processing
                         Foam Decontamination
                         Chemical Gels
                    4.4.11 Selection of Chemical Decontamination Processes
               4.5 Mechanical Decontamination Techniques
                    4.5.1 Overview
                    4.5.2 Water Flushing
                    4.5.3 Dusting/Vacuuming/Wiping/Scrubbing
                    4.5.4 Steam Cleaning
                    4.5.5 CO2: Blasting
                    4.5.6 Wet-Ice Blasting
                    4.5.7 Hydroblasting
                    4.5.8 Ultra-High-Pressure Water
                    4.5.9 Shot Blasting
                    4.5.10 Wet Abrasive Cleaning
                    4.5.11 Grit Blasting
                    4.5.12 Grinding
                    4.5.13 Scarifiers
                         Scabbling
                         Needle Scaling
                         Applications
                    4.5.14 Milling
                    4.5.15 Drill and Spall
                    4.5.16 Paving Breaker and Chipping Hammer
                    4.5.17 Expansive Grout
                    4.5.18 Asbestos Removal
               4.6 Other Decontamination Techniques
                    4.6.1 Electropolishing
                         Description of Technique
                         Electrolytes
                         H3PO4: Electrolytes
                         HNO3: Electrolytes
                         Organic Acid Electrolytes
                         Applications
                    4.6.2 Ultrasonic Cleaning
                    4.6.3 Vibratory Finishing*6pt
          5: Cutting and Dismantling Techniques
               5.1 Overview
               5.2 Thermal Cutting Techniques
                    5.2.1 Gas Processes
                         Powder Injection Flame Cutting
                         Flame Cutting
                         Flame Gouging
                         Oxygen Lance Cutting
                    5.2.2 Arc Processes
                         Oxy-Arc Cutting
                         Consumable Electrode Oxygen Jet Cutting
                         Consumable Electrode Water Jet Cutting
                         Contact ArcMetal Cutting
                         Electrical Discharge Machining
                         Arc-Saw Cutting
                         Consumable Electrode Water Jet Gouging
                    5.2.3 Plasma-Arc Processes
                         Plasma-Arc Cutting with Single Torch
                         Plasma Compass Saw Cutting and Plasma Circular Saw Cutting
                         Plasma Compass Saw
                         Plasma Circular Saw
                         Plasma-Arc Gouging
                    5.2.4 Laser Cutting
                    5.2.5 Combined Cutting Processes
                         Consumable Electrode Water Jet Gouging/Flame Cutting
                         Plasma Arc Gouging/Flame Cutting
               5.3 Hydraulic Cutting Techniques
                    5.3.1 High Pressure Water Jet Cutting
                    5.3.2 Abrasive Water Jet Cutting
               5.4 Mechanical Dismantling Techniques
                    5.4.1 Grinder
                    5.4.2 Hacksaw and Guillotine Saw
                    5.4.3 Shears
                    5.4.4 Milling Cutters and Orbital Cutters
                    5.4.5 Knurl Tube Cutter
                    5.4.6 Diamond Saws and Cables
                         Diamond Saws
                         Diamond Cables
               5.5 Conclusions
          6: Remote Control Techniques
               6.1 Basis of Remote Operation
                    6.1.1 Overview
                    6.1.2 Safety Enhancement
                    6.1.3 Cost Reduction
                    6.1.4 Productivity Improvement
                    6.1.5 Utilization of Facility Resources
                    6.1.6 Accessibility
                    6.1.7 Disadvantages of Remote Operation
               6.2 Remote Operation Technologies
                    6.2.1 Overview
                    6.2.2 Detection Equipment
                         Cameras and Lights
                         Other Detectors
                    6.2.3 Segmenting and Demolishing Equipment
                    6.2.4 Decontamination Equipment
                    6.2.5 Material-Handling Equipment
                    6.2.6 Sampling Equipment
                    6.2.7 Hand-Held Equipment
               6.3 Remote-System Configurations
                    6.3.1 Overview
                    6.3.2 Control Stations
                         Teleoperator Control Stations
                         Teleoperator Managed Stations
                         Automated Stations
                    6.3.3 Communication and Power Links
                    6.3.4 Support Platforms
                    6.3.5 Arms
                         Existing Equipment
                         Robots
                         Speciality Systems
                    6.3.6 End Effectors and Tools
               6.4 Illustrative Experiences with Remote Applications
                    6.4.1 Detection Equipment
                    6.4.2 Sampling Equipment
                    6.4.3 Hand-Held Equipment
                    6.4.4 Miscellaneous Equipment
          7: Spent-Fuel and Waste Management
               7.1 Spent-Fuel Interim Storage
                    7.1.1 Wet Interim Storage
                         Pool Re-Racking
                         Spent-Fuel Consolidation
                         Independent Wet Storage Pool
                    7.1.2 Dry Interim Storage
                         Metal Casks
                         Vaults
                         Concrete Casks
                         Concrete Silos
                         NUHOMS Modular System
               7.2 Waste Management
                    7.2.1 Overview
                    7.2.2 Clearance Levels
                    7.2.3 Waste-Management Strategy
                    7.2.4 Waste-Management Arrangements
                    7.2.5 Treatment and Conditioning of Liquid Wastes
                    7.2.6 Treatment and Conditioning of Solid Wastes
                    7.2.7 Treatment and Conditioning of Gaseous and Aerosol Wastes
                    7.2.8 Packaging and Storing Technologies
                    7.2.9 Waste Transport
                    7.2.10 Waste Characterization and Measurement Techniques
                         CharacterizationMethods
                         Gross Gamma Measurement
                         Gamma Spectrum Analysis
                         Energy-Sensitive Detectors
                         Instrumentation
                         Gas Filled Detectors
                         Scintillation Detectors
                         Solid-State Detectors
                         Special Alpha Techniques
                         Waste Characterization Program
               7.3 The Waste Management Facility (WMF)
                    7.3.1 WMF Design Criteria
                    7.3.2 Description of the Areas and the Equipment
                         Segmentation
                         Decontamination
                         Volume Reduction
                         Immobilization by Grouting
                         Monitoring, Characterization and Release
                         Interim Storage Areas (Buffers)
                    7.3.3 Staff Requirements
          8: Safety, Health and Environmental Protection
               8.1 Overview
               8.2 Safety Culture
               8.3 Safety Assessment
                    8.3.1 Accident Analysis
                    8.3.2 Human Factors and Organizational Considerations
                    8.3.3 Emergency Planning
               8.4 Environmental Impact Assessment (EIA)
                    8.4.1 Scoping
                    8.4.2 Environmental Impact Evaluation
                    8.4.3 EIA Regulations
                    8.4.4 Consent Processes for Decommissioning in EU Member States
                    8.4.5 Consultation and Public Participation
                    8.4.6 Definition of Preferred Options
                    8.4.7 Baseline Description
                         Impact Factors Relating to the Natural Environment
                         Identification of Potential Impacts
                    8.4.8 Impact Assessment
                         Impact Indicators
                         Radiological Impacts
                         Noise and Vibrations
                         Air Quality
                         Land Use
                         Results of Assessment
                    8.4.9 Mitigation Measures
                         Identification ofMitigationMeasures
                         Final Impact
                    8.4.10 Environmental Surveillance Program
          9: Decommissioning Cost Evaluation
               9.1 Cost Evaluation Methodologies
               9.2 Account Presentation
               9.3 Responsibilities and Financing
               9.4 Standard Criteria for Cost Evaluation
               9.5 Cost Evaluations
                    9.5.1 Overview
                    9.5.2 Cost-Assessment Methods
               9.6 Cost Calculation Model Example
                    9.6.1 Cost-Breakdown Structure
                    9.6.2 Mass Analysis
                         Primary Masses
                         Secondary Masses
                         TertiaryMasses
                    9.6.3 Calculation of Decommissioning Activities
                         Decommissioning Cost
                         Employable Technology
                         Necessary Tools and Equipment
                         Other Articles of Consumption
                         Required Manpower and Duration
                         Expected Personnel Radiation Exposure
               9.7 International Comparisons
                    9.7.1 Overview
                    9.7.2 Variations in Cost Estimates
                    9.7.3 Cost Estimates in the USA
                    9.7.4 Cost Estimates in Europe
          10: International Organizations Roles
               10.1 UNO-IAEA (United Nations Organization-International Atomic EnergyAgency)
               10.2 OECD-NEA (Organization for Economic Cooperation andDevelopment)
               10.3 EC (European Commission)
               10.4 WANO (World Association of Nuclear Operators)
               10.5 WENRA (West European Nuclear Regulator Association)
          References
               UNO-IAEA Documents
               OECD-NEA Documents
               EU Documents
               US-NRC Documents
          Further Reading
               Other Organizations
               Other Documents
     28: The Scientific Basis of Nuclear Waste Management
          1: Generalities on Waste
               Definitions
               1.1 Origin, Nature, Volume, and Flux of Waste
                    1.1.1 Waste Classification
                    1.1.2 Volume and Flux of Waste
                    1.1.3 Which Radionuclides in the Spent Fuel?
                    1.1.4 Fission Products Are Radioactive
                    1.1.5 Formation of Transuranic Isotopes in the Reactor Core
                    1.1.6 Radioactive Decay
                    1.1.7 What Kind of Radioactive Emission Do We Expect from theNuclear Waste?
                    1.1.8 Penetration of Ionizing Radiations into Matter
                    1.1.9 The Radioactive Half-Life of the Main Radionuclides Found inNuclear Waste
                    1.1.10 Radioactive Waste: How Dangerous Is It?
               1.2 Management Options: An Overview
                    1.2.1 Dispersion or Concentration?
                    1.2.2 Waste, Effluents, Decontamination, and Conditioning: A SystemicVision
                    1.2.3 Reprocessing or Not Reprocessing?
                    1.2.4 World Situation for Waste Management
                    1.2.5 The Institutions In Charge of Waste Management in the World
                    1.2.6 The Waste Management Process
                    1.2.7 Uranium Mine Tailing Management
                    1.2.8 Management of Low and Intermediate Level, Short-LivedWaste (LIL-SL)
                    1.2.9 Interim Storage of Spent Fuel
                    1.2.10 High Activity Waste from Reprocessing is Vitrified
                    1.2.11 Options for the Management of Long-Lived Nuclear Waste
                         Partitioning and Transmutation
                         Conditioning
                         Interim Storage
                         Deep Geological Disposal
                    1.2.12 Waste Management and Radioprotection
                    1.2.13 From Radioactivity to Radiotoxicity
                    1.2.14 Ingestion Dose Factors
                    1.2.15 The Long-Term Radiotoxicity of Spent Fuel
                    1.2.16 Deep Geological Disposal: The Multibarrier Concept
          2: Waste Conditioning
               2.1 Conditioning of LL and IL Waste in Cement-Based Matrices
                    2.1.1 Elaboration of Cement-Based Materials
                    2.1.2 Waste Conditioning in Cement-Based Materials
                    2.1.3 Long-Term Behavior of Cement-Based Materials
                    2.1.4 R&D on Cement-Based Materials for Waste Conditioning
                    2.1.5 Waste Container Manufacturing
               2.2 Conditioning of HL-LL Waste in Glass
                    2.2.1 Vitrification of Solutions of Fission Products
                    2.2.2 Requirements for the Glass Material
                    2.2.3 Physicochemistry of Glass
                    2.2.4 Glass Composition
                    2.2.5 Incorporation of Radionuclides in Glass: Where Is the Limit?
                    2.2.6 Glass Fabrication: The Hot Crucible Vitrification Process
                    2.2.7 The Vitrified Waste Package
                    2.2.8 Cold Crucible Vitrification
                    2.2.9 Long-Term Behavior of Glass
                    2.2.10 Long-Term Behavior of Glass in Contact with Water
                    2.2.11 Phenomenology of Glass Alteration by Water
                    2.2.12 Glass Alteration by Water Depends Greatly on Temperature
                    2.2.13 Toward a Model of Glass Alteration
                         Hypotheses
                    2.2.14 The Residual Alteration Regime of Glass
                    2.2.15 Long-Term Behavior of Glass: The Effect of Self-Irradiation
               2.3 Other Conditionings for Waste
                    2.3.1 Bituminization of Low- or Intermediate-Level Waste
                    2.3.2 Bitumen Manufacturing
                    2.3.3 Bitumen Package Evolution Under Self-Irradiation
                    2.3.4 Bitumen Alteration by Water
                    2.3.5 Conditioning of Fuel Claddings and End Caps
                    2.3.6 The Long-Term Behavior of the Compacted Metallic Waste Package
                    2.3.7 Melting: A Possible Future Conditioning for Metallic Waste
                    2.3.8 Specific Conditioning for Minor Actinides and Fission Products
               2.4 Conditioning of Spent Fuel
                    2.4.1 Can Spent Fuel Be a Conditioning Matrix?
                    2.4.2 Spent Fuel Evolution After Unloading
                    2.4.3 Packaging Spent Fuel
                    2.4.4 Choice of the Container Material
                    2.4.5 Corrosion Rates of Low-Alloyed Steels
                    2.4.6 Post-Irradiation State of the Spent Fuel
                         Irradiated Clad State
                         Post-Irradiation Physical State of Spent Fuel Pellet
                    2.4.7 Fuel Evolution in a Closed System
                    2.4.8 Spent Fuel in a Water-Saturated Repository
                    2.4.9 Conclusion on the Storage and Direct Disposal of Spent Fuel*6pt
          3: Waste Storage and Disposal
               3.1 Interim Storage of Long-Lived Waste and Spent Fuel
                    3.1.1 Storage: A Temporary Solution for Waste Management
                    3.1.2 An Important Stake of Interim Storage: Reduce the Cost of the Disposal
                    3.1.3 The Objects To Be Stored
                    3.1.4 The Storage Facilities for Long-Lived Waste
                    3.1.5 Duration of the Interim Storage
               3.2 Geological Disposal
                    3.2.1 The General Principles of Deep Geological Disposal
                    3.2.2 The Technical Principles of Deep Geological Disposal
                    3.2.3 The Multibarrier Concept
                    3.2.4 Repository Lifetime
                    3.2.5 Repository Architecture
                         Dimensions of a High-Level Repository
                    3.2.6 Cost of an HL LL Waste Repository
                    3.2.7 The Foreseen Evolution of a Repository
                         The First One Thousand Years
                         10,000 Years On and More
                         Millions of Years On
                    3.2.8 Geodynamic Evolution of a Deep Geological Repository
                    3.2.9 The Criteria for the Choice of a Suitable Location for a DeepGeological Repository
                    3.2.10 Choice of the Host Rock for the Waste Disposal
                    3.2.11 Hydrogeology
                    3.2.12 Calculation of Water Flow in a Permeable Porous Medium
                    3.2.13 Radionuclide Migration
                    3.2.14 Kinematic Dispersion
                    3.2.15 The Tracer Equation
                    3.2.16 Characteristic Migration Time Through a Geological Barrier
                    3.2.17 Sorption of a Non-Perfect Tracer
                    3.2.18 Migration of a Sorbing Tracer
                    3.2.19 Migration of Actinides
                    3.2.20 Radionuclide Speciation and Solubility Limits
                    3.2.21 Porewater Chemistry
                    3.2.22 How to Evaluate the Transport of RN Underground
                    3.2.23 Validation of the Models of RN Transport Underground
                    3.2.24 Thermo-Hydro Mechanico-Chemical Effects in the Near-Fieldof a Geological Repository
                    3.2.25 Thermal Behavior of High-Activity Waste
                    3.2.26 Chemical Phenomena in the Near-Field
                         Redox Front Propagation
                         Dissolution–Precipitation
                         Corrosion
                    3.2.27 Mechanical Behavior of a Repository
                    3.2.28 Mechanical Effects Due to the Excavation of the Galleries
                    3.2.29 Hydraulic Effects
                    3.2.30 Hydro-Mechanical Effects in the Near-Field
                    3.2.31 Hydro-Chemical Couplings in the Near-Field
                    3.2.32 Gas Production and Release in an Underground Repository:An Example of H–M–C Coupling
                    3.2.33 Underground Laboratories
                    3.2.34 Natural Analogues Can Help Validate the Models of Long-TermBehavior of a Repository: The Example of Oklo
               3.3 Safety of Waste Disposal Facilities
                    3.3.1 How to Evaluate the Radiological Impact of a Deep GeologicalRepository?
                    3.3.2 Evaluation of the Order of Magnitude of the Activity at the Exutory fora Simplified Repository
                    3.3.3 The Source-Term
                    3.3.4 Transit Time from the Repository to the Exutory
                    3.3.5 Transfer Through the Geosphere
                    3.3.6 Activity at the Exutory
                    3.3.7 Evaluation of the Order of Magnitude of the Dose to Man
          4: Conclusions
               4.1 Waste: The Achilles' Heel of the Nuclear Industry?
               4.2 Technical Solutions and Political Advances for Waste Management
               4.3 The Main Principles of Nuclear Waste Management
               4.4 Recycling: The First Link of the Waste Management Chain
               4.5 Transmute, Recycle: Where Is the Limit?
               4.6 Waste Conditioning: The Essential Second Link in the Chain ofWaste Management
               4.7 What To Do with the Final Waste?
               4.8 Interim Storage, A Temporary Solution That Gives Flexibility tothe Management of Waste
               4.9 Underground Disposal, The Last Link of the Chain: A Final Placefor the Final Waste
               4.10 Underground Disposal: A Simple and Robust Concept
               4.11 Let Us Behave Responsibly, Let Us Try To Be Sensible
          5: Glossary
          References
     29: Proliferation Resistance and Safeguards
          1: Proliferation Resistance
               1.1 Material Attractiveness
                    1.1.1 Figure of Merit
                    1.1.2 Meaning of FOM Values
                    1.1.3 Comparison of Various Reprocessing Schemes
                    1.1.4 Conclusions
               1.2 Nonproliferation Impact Assessments
                    1.2.1 Methodology
                    1.2.2 Technical Factors and Metrics
                    1.2.3 Policy Factors and Grading
                    1.2.4 PR&PP Example
          2: Safeguards
               2.1 Domestic Safeguards: Implementing a State System ofAccounting and Control (SSAC)
                    2.1.1 Primary Features of an SSAC
               2.2 IAEA Inspection Regime
                    2.2.1 Timeliness Goals
                    2.2.2 Quantity Goals
                    2.2.3 Deterrence by Risk of Early Detection
                    2.2.4 Frequency of Inspection to Fulfill Technical Objectives of Safeguards
                    2.2.5 IAEA Nuclear Facility Categories
                    2.2.6 Keystones of Bookkeeping, Material Accountancy, andContainment and Surveillance
                    2.2.7 Strengthened Safeguards
               2.3 Safeguards Design
                    2.3.1 Safeguards Requirements
                    2.3.2 Safeguards by Design
               2.4 Unattended Monitoring
                    2.4.1 Background
                    2.4.2 Definition of an Unattended Monitoring System (UMS)
                    2.4.3 Why Does the IAEA Use UMS?
                    2.4.4 Benefits of UMS
                    2.4.5 Key to Maintaining a Balanced Approach in IAEA Safeguards
                    2.4.6 Major Cost Drivers in the Department of Safeguards
                    2.4.7 Primary Goals of UMS
                    2.4.8 Method of Obtaining Primary Goals
                    2.4.9 Conclusion
               2.5 Process Monitoring
                    2.5.1 Key Elements
                    2.5.2 Role of Models and Simulation
                    2.5.3 Strategy for Reprocessing Plants
                    2.5.4 Operational Evaluation Systems
               2.6 Environmental Sampling
                    2.6.1 Basic Principles of Environmental Sampling
                    2.6.2 Sampling Methods
                    2.6.3 Bulk Measurements of Dust Samples
                    2.6.4 Particle Measurements of Dust Samples
               2.7 Forensics
                    2.7.1 Methodology
                    2.7.2 Characteristic Parameters in Nuclear Forensic Investigations
                    2.7.3 Data Interpretation and Attribution
                    2.7.4 Conclusions
               2.8 Statistics for Accountancy
                    2.8.1 Background
                    2.8.2 Measurement Error Models
                    2.8.3 Propagation of Variance
                    2.8.4 Sequential or Trend Testing
                    2.8.5 ID Test
                    2.8.6 SITMUF Test
                    2.8.7 Verifying Declarations
                    2.8.8 Other Purposes of the PI
                    2.8.9 Sampling
                    2.8.10 Difficulties with ID Evaluation
                    2.8.11 Solution Monitoring
                    2.8.12 Conclusions
               2.9 Accountancy for Abrupt Diversion
          References
          Website
Index