Neutronics of advanced nuclear systems / Yican Wu.

Intro; Foreword I; Foreword II; Foreword III; Preface; Contents; 1 Introduction; 1.1 The Development of Nuclear Systems; 1.1.1 Basic Principles of Nuclear Energy Generation; 1.1.2 The Development of Nuclear Systems; 1.2 Brief Introduction to Advanced Nuclear Systems; 1.2.1 Advanced Fission Systems; 1.2.2 Fusion Systems; 1.2.3 Hybrid Nuclear Systems; 1.3 Neutronics Research Overview of Advanced Nuclear Systems; 1.3.1 Neutronics Characteristics; 1.3.2 Research Content; References; Neutronics Theories and Methodologies; 2 Steady-State Neutron Transport Theory and Simulation

2.1 Neutron Transport Theory2.1.1 Interaction of Neutrons with Matter; 2.1.2 Foundation of Neutron Transport Theory; 2.2 Monte Carlo Computational Methods; 2.2.1 Basic Principles; 2.2.2 Estimation Methods for Physical Quantities; 2.2.3 Acceleration Methods; 2.3 Deterministic Computational Methods; 2.3.1 The Discrete Ordinates Method; 2.3.2 The Method of Characteristics; 2.3.3 The Spherical Harmonics Method; 2.3.4 Acceleration Methods; 2.4 MC and Deterministic Coupling Calculations; 2.4.1 Region Coupling Method; 2.4.2 Energy Coupling; 2.5 Transport Simulation Codes; 2.5.1 Monte Carlo Codes

2.5.2 Deterministic CodesReferences; 3 Neutron Kinetics; 3.1 Physical Basis of Neutron Kinetics; 3.1.1 Basic Concepts; 3.1.2 Kinetic Equations; 3.2 Characteristics of Neutron Kinetics in Advanced Nuclear Systems; 3.3 Computational Methods for Kinetics Problems in Advanced Nuclear Systems; 3.3.1 Direct Numerical Method; 3.3.2 Modal Expansion Method; 3.3.3 Factorization Method; 3.4 Simulation Codes for Neutron Kinetics; References; 4 Neutron-Induced Transmutation; 4.1 Principles of Transmutation; 4.2 Nuclear Transmutation Process; 4.2.1 Burnup; 4.2.2 Nuclear Waste Transmutation

4.2.3 Nuclear Fuel Breeding4.2.4 Material Activation; 4.3 In-core Fuel Management and Fuel Cycle; 4.3.1 Fission Fuel Management and Fuel Cycle; 4.3.2 Fusion Tritium Cycle; 4.4 Nuclear Transmutation Calculation; 4.4.1 Calculation Methods; 4.4.2 Simulation Codes; References; 5 Radiation Dosimetry and Biological Safety; 5.1 Radioactive Source and Nuclide Migration; 5.1.1 Radioactive Source Terms; 5.1.2 Radionuclide Migration in Nuclear Systems; 5.1.3 Radionuclide Migration in the Environment; 5.2 Radiation Dosimetry Calculations; 5.2.1 Dosimetric Quantities in Radiological Protection

5.2.2 External Exposure Calculation5.2.3 Internal Exposure Calculation; 5.3 Biological Effects of Radiation; 5.3.1 Basic Principles; 5.3.2 Biological Effects of Neutrons; 5.3.3 Biological Effects of Fission Products; 5.3.4 Biological Effects of Neutron Activation Products; 5.3.5 Biological Effects of Tritium; References; 6 Material Neutron Irradiation Damage; 6.1 Mechanisms of Neutron Irradiation Damage; 6.1.1 Interactions Between Neutron and Materials; 6.1.2 Displacement Damage; 6.2 Effects of Neutron Irradiation on Material Microstructures; 6.2.1 Formation and Evolution of Point Defects