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Global Neutron Calculations

  • ID: 3265331
  • Book
  • March 2015
  • Region: Global
  • 576 Pages
  • Bentham Science Publishers Ltd
Global Neutron Calculations provides assessment guidelines for nuclear reactors in a step-by-step manner. The book introduces readers to principal physical ideas, the fundamentals of nuclear reactors including the theory of self-sustaining chain reactions and the associated physical and mathematical calculations. The required theory, the mathematical appparatus and, the applied methods are comprehensively explained in the first half of the book followed by details about the applications of the theory and methods.

Readers will gain essential information about reactor control and surveillance, instrumentation and control, technology, fuel management, core design and the differences in reactor technologies.

Global Neutron Calculations demystifies technical and mathematical knowledge about reactor design, operation, safety and analysis for engineers learning about one of mankind’s most controversial means of power generation.
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1. Reactor Calculations

1. Self-sustaining chain reaction
2. Reactor physics models
3. Applications of reactor codes
4. Validation and veri?cation
5. Regulation questions
6. Surveillance of nuclear reactors

2. Foundation of Core Calculations

1. Nuclear physics of fission
2. Neutron field in a nuclear reactor
3. Integral transport equation
4. Adjoint function

3. Solutions of the Transport Equations

1. Green’s function
2. Case method
3. Perturbation theory, variational methods, response matrix
4. The heat side of the problem

4. Approximate Solutions

1. Asymptotic theory
2. Energy groups
3. Pn method
4. Sn method
5. Collision probability method
6. Randomness in the neutron field
7. Monte Carlo method

5. Calculational Model

1. Cell calculation
2. Assembly calculation
3. Full core calculation
4. Re?ector calculation
5. Burnup calculations

6. Neutron Diffusion

1. Derivation of the diffusion equation
2. Mathematical properties of the diffusion equation
3. Derivation and limitations
4. One group diffusion theory
5. Few group diffusion theory
6. Response matrices in diffusion theory
7. Time dependence in diffusion theory

7. Neutron Spectrum

1. Fast neutrons
2. Slowing down
3. Resonance region
4. Thermalization
5. Fermi age
6. Validation and veri?cation

8. Numerical Methods

1. Finite difference
2. Finite elements
3. Nodal methods
4. Thermal hydraulics

9. Kinetics

1. Reactor kinetics
2. Approximate solution of the time dependent DE
3. Reactivity measurement

10. In-Core Measurements

1. The goal of core surveillance
2. Measured fields
3. Measurement techniques
4. Core monitoring
5. Measurement and safety
6. Core monitoring in Generation III reactors
7. Core surveillance at VVER-440 reactors: an example

11. Core Design Methods

1. Power distribution limits
2. Calculational model and reactor operation
3. Core optimization
4. Equilibrium fuel cycle
5. Reactivity coeficients and feedbacks
6. Regulation of the reactor
7. Safety issues

12. Nuclear Reactors

1. Nuclear reactors for electricity production
2. Nuclear power plant types and generations
3. Technology of nuclear power stations with PWR technology
4. Safety - defense in depth principle for Generation III plants

13. Acronyms

Appendix A. Mathematics Fundamentals

1. General
2. Theorems applied in the text
3. Special functions

Appendix B. Some Thermal Hydraulics Codes

1. System codes
2. CFD codes

Appendix C. Statistical Physics in Noise Analysis

Appendix D. A Simple Reactor Model

Appendix E. Mathematical Properties of Operators

1. Eigenvalue problem
2. Applications

Appendix F. Symmetries of the Transport Operator

1. Boundary value problem
2. Symmetries
3. Symmetries of the Boltzmann transport equation
4. Symmetries and boundary values
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