Principles of Radiation Shielding
by Arthur B. Chilton, J. Kenneth Shultis and Richard E. Faw
Prentice-Hall, Englewood Cliffs, NJ, 1984. ISBN 0-13-709907-X
Table of Contents
Preface
Chapter 1. Introduction
Chapter 2. Characterization of Radiation Fields and Sources
2.1 Fundamental radiation field variables
2.2 Directional properties of the radiation field
2.3 Dosimetric quantities of a purely physical nature
2.4 Radiation quantities closely related to biological risk
2.5 General source properties
2.6 Conversion from distributed to discrete concepts, and vice versa
Chapter 3. Interaction of Radiation with Matter
3.1 Interaction coefficient
3.2 Microscopic cross section
3.3 Cross sections for photon interactions
3.4 Photon attenuation coefficients
3.5 Photon absorption coefficients and related quantities
3.6 Cross sections for neutron interactions
3.7 Neutron scattering interactions
3.8 Radiative capture
3.9 Penetration of charged particles through matter
Chapter 4. Common Radiation Sources Encountered in Shield Design
4.1 Neutron sources
4.2 Sources of gamma photons
4.3 Sources of x rays
Chapter 5. Detector Response Functions
5.1 General formulation for dosimetric detectors
5.2 Relationship of kerma rate and absorbed dose rate; charged particle equilibrium
5.3 Neutron kerma, absorbed dose, and dose equivalent
5.4 Dosimetric response functions for photons
5.5 Response functions for evaluation of hazards to human beings
5.6 Concluding remarks
Chapter 6. Basic Concepts in Neutral Particle Penetration
6.1 Uncollided-particle attenuation and mean free path
6.2 Total detector response
6.3 Approximation formulas for total response
6.4 Ray analysis technique
6.5 Point kernel
6.6 Geometric transformations
6.7 Special concepts useful for design purposes
Chapter 7. Special Techniques in Photon Attenuation
7.1 Photon buildup-factor concept
7.2 Buildup-factor values and empirical approximations
7.3 Complex aspects of the buildup factor
7.4 Extension of point-kernel techniques to incorporate buildup
7.5 Special techniques for medical facilities
Chapter 8. Special Techniques in Neutron Attenuation
8.1 Difference between fast-neutron and photon flux density calculations
8.2 Attenuation of fast neutrons from fission sources in hydrogenous media
8.3 Removal cross section
8.4 Fast-neutron attenuation in nonhydrogenous media
8.5 Calculation of intermediate and thermal flux densities
8.6 Capture-gamma-photon attenuation
8.7 Neutron shielding by Concrete slabs
Chapter 9. Approximate Techniques Under Special Geometric Conditions
9.1 Albedo concept
9.2 Radiation streaming through ducts
9.3 Treatment of shield heterogeneities
Chapter 10. The Transport Description of Radiation Penetration
10.1 Transport equation
10.2 Approximations to the transport equation
10.3 Method of moments
10.4 Discrete-ordinates method
10.5 Monte Carlo method
Chapter 11. Material and Structural Considerations in Shield Design
11.1 Material properties
11.2 Radiation damage
11.3 Thermal effects
11.4 Thermal-mechanical interactions
Appendices
1. Constants and Conversion Factors
2. Mathematical Functions of Importance in Shielding Analysis
3. Cross Sections and Related Data for Photon and Neutron Interactions
4. Buildup Factors for Gamma Photons
5. Decay Characteristics of Selected Radionuclides
6. Parameters for Use in Calculating Fission-Product Photon Source Strengths
Index