Computational Methods in Reactor Shielding
- 1st Edition - October 22, 2013
- Author: James Wood
- Language: English
- eBook ISBN:9 7 8 - 1 - 4 8 3 1 - 4 8 1 3 - 7
Computational Methods in Reactor Shielding deals with the mathematical processes involved in how to effectively control the dangerous effect of nuclear radiation. Reactor shielding… Read more
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Request a sales quoteComputational Methods in Reactor Shielding deals with the mathematical processes involved in how to effectively control the dangerous effect of nuclear radiation. Reactor shielding is considered an important aspect in the operation of reactor systems to ensure the safety of personnel and others that can be directly or indirectly affected. Composed of seven chapters, the book discusses ionizing radiation and how it aids in the control and containment of radioactive substances that are considered harmful to all living things. The text also outlines the necessary radiation quantities and units that are needed for a systemic control of shielding and presents an examination of the main sources of nuclear radiation. A discussion of the gamma photon cross sections and an introduction to BMIX, a computer program used in illustrating a technique in identifying the gamma ray build-up factor for a reactor shield, are added. The selection also discusses various mathematical representations and areas of shielding theory that are being used in radiation shielding. The book is of great value to those involved in the development and implementation of systems to minimize and control the dangerous and lethal effect of radiation.
Chapter 1 Introduction
1.1 The Shielding Problem
1.2 Scope of the Book
1.3 Background Knowledge
1.4 The Computer Programs
1.5 References
Chapter 2 Radiation Quantities and Units
2.1 Some Preliminary Considerations Relating to Radiological Protection
2.2 Recommended Radiation Levels
2.3 General Environmental Radiation Levels
2.4 Radiation Quantities and Units
2.5 Conversion of Radiation Intensity to Dose Equivalent Rate
2.6 A more Mathematical Treatment of the Basic Transport Quantities
2.7 The Albedo Concept
2.8 References
Chapter 3 Radiation Sources
3.1 Nuclear Reactors
Primary Radiation
Secondary Radiation
3.2 Radioactive Sources
3.3 Particle Accelerators
3.4 Reactor Coolant Activation
3.5 Miscellaneous Topics
3.6 References
Chapter 4 The Attenuation of Gamma Rays
4.1 Narrow Beam Attenuation
Photon Atomic Cross Sections
4.2 Broad Beam Attenuation
Buildup Factor: The Basic Idea
Empirical Formula for B(µr)
4.3 The Computer Program BMIX
4.4 Exercises for Program BMIX
4.5 References
Chapter 5 Applications of the Point Kernel Technique
5.1 The Mathematical Representation of Detector Response
5.2 Geometrical Transformations
5.3 Examples in the Use of the Point Kernel Technique
5.4 CASK: A Simple Shielding Program for Spherical Sources of Nuclear Radiation
5.5 Modification of Program CASK to Include a Line Source
5.6 Exercises for Program CASK
5.7 Exercises for Modified Form of CASK
5.8 References
Chapter 6 Neutron Attenuation
6.1 The Basic Strategy
6.2 Neutron Removal Cross Section
6.3 Theoretical Treatment of Fast Neutron Attenuation
Empirical Neutron Point Kernels
6.4 Removal Diffusion Theory
Spinney Removal Method
Multigroup Diffusion Equations
6.5 The Computer Program CADRE
6.6 Exercises for Program CADRE
6.7 Shield Optimization
6.8 References
Chapter 7 Transport Theory Methods
The Derivation of the Boltzmann Transport Equation
7.1 The Monte Carlo Method
Techniques for Random Sampling
The Estimation of Monte Carlo Error
Variance Reduction Techniques
Generating Random Numbers
The Computer Program TESR
Buffon's Needle Experiment
The Computer Program KLEIN
Monte Carlo Computer Program Monteray Mark I
Extended Version of Program Monteray
The Application of the Monte Carlo Method to Neutron Problems
The Computer Program ELSCAT
7.2 The Moments Method
The Boltzmann Equation for the Energy Flux
The P1 Equations
The Kernel for Compton Scattering
The Dimensionless Form of the Equations
The Moments of the Flux
Construction of Flux Distributions from the Moments
The Computer Program DBUF
7.3 References
Appendixes
Appendix A The Dirac Delta-Function
Appendix B Coordinate Systems, the Gradient Operator V, and the Laplacian Operator V2
Appendix C Selected Nuclear Data
Appendix D SI Units in Radiation and Radioactivity
Index
- No. of pages: 450
- Language: English
- Edition: 1
- Published: October 22, 2013
- Imprint: Pergamon
- eBook ISBN: 9781483148137
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