Calculational Methods for Interacting Arrays of Fissile Material - 1st Edition - ISBN: 9780080176604, 9781483156613

Calculational Methods for Interacting Arrays of Fissile Material

1st Edition

International Series of Monographs in Nuclear Energy

Authors: A. F. Thomas F. Abbey
Editors: D. J. Silverleaf
eBook ISBN: 9781483156613
Imprint: Pergamon
Published Date: 1st January 1973
Page Count: 140
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Calculational Methods for Interacting Arrays of Fissile Material describes the methods used in assessing the criticality safety of interacting arrays of fissile materials. It demonstrates that the behavior of neutrons in an array can be divided into two parts which can, to a large extent, be treated independently. These are the neutron multiplication within units of the array and the transmission of neutrons between units. For the former the usual methods of neutron physics are applicable but used so as to place emphasis on the neutrons entering and leaving the unit. The latter is mainly a geometrical problem, being entirely so for an air-spaced array. This volume is comprised of four chapters and begins with an introduction to the practical aspects of the interaction problem affecting arrays of fissile materials. The discussion then turns to simple ""hand"" methods of calculation, paying particular attention to the general equilibrium conditions in interacting arrays, along with the Oak Ridge method, the Interaction Parameter method, and the PQR method. Finally, the application of Monte Carlo method to the study of the neutron economy of entire arrays is considered in terms of one particular computer code called GEM. The basis of neutron tracking in critical size calculations by GEM is analyzed. This book will be a valuable resource for nuclear engineers and scientists.

Table of Contents



1. The General Nature of the Interaction Problem

2. The Problem in Practice

3. Simple Hand Methods

3.1. General Equilibrium Conditions in Interacting Arrays

3.1.1. Conditions for Criticality

3.1.2. Factors Affecting c

3.1.3. More Detailed Description of Neutron Flow

3.2. The Oak Ridge Method

3.2.1. Experimental Basis of the Method

3.2.2. Safety Criteria for Bare Containers

3.2.3. Effects of Full and Partial Reflection

3.2.4. Interaction between Dissimilar Units

3.2.5. Other Factors Affecting Interaction in the ORGDP Method

3.2.6. Summary of the Method and Formula for Solid Angle and k

3.2.1. Later Work

3.3. The Interaction Parameter Method

3.3.1. Application of the Condition for Criticality

3.3.2. Experimental Measurement of Interaction Parameters

3.3.3. Estimation of Interaction Parameters from Multiplication Values

3.3.4. Some Applications of the Interaction Parameter Method

3.4. Comparison of the Oak Ridge Method and the Interaction Parameter Method

3.4.1. Upper Limit to Ms in Terms of k

3.4.2. Numerical Examples and Checks

3.4.3. On the Interaction between Pairs of Dissimilar Containers

3.5. The PQR Method

3.5.1. General Theory

3.5.2. Application of the PQR Method

4. Monte Carlo Methods

4.1. GEM

4.1.1. Neutron Tracking

4.1.2. Neutron Counts and Prints

4.1.3. Specification of a GEM Calculation and Interpretation of the Print out

4.1.4. External Source Calculations

Appendix I. Solution of the Critical Equations by Matrix Iteration




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© Pergamon 1973
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About the Author

A. F. Thomas

F. Abbey

About the Editor

D. J. Silverleaf

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