Authors: Mihály Makai, Dániel Péter Kis, János Végh

Global Neutron Calculations

eBook: US $236 Special Offer (PDF + Printed Copy): US $378
Printed Copy: US $260
Library License: US $944
ISBN: 978-1-68108-028-4 (Print)
ISBN: 978-1-68108-027-7 (Online)
Year of Publication: 2015
DOI: 10.2174/97816810802771150101

Introduction

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.

Indexed in: Book Citation Index, Science Edition, EBSCO.

Foreword

- Pp. i-iii (3)
Paul Zweifel
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Preface

- Pp. v-vii (3)
Mihály Makai
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Credits

- Pp. ix-x (2)
Mihály Makai, Dániel Péter Kis, János Végh
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Reactor Calculations

- Pp. 1-13 (13)
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Foundation of Core Calculations

- Pp. 15-66 (52)
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Solutions of the Transport Equations

- Pp. 67-106 (40)
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Approximate Solutions

- Pp. 107-170 (64)
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Calculational Model

- Pp. 171-191 (21)
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Neutron Diffusion

- Pp. 193-228 (36)
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Neutron Spectrum

- Pp. 229-273 (45)
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Numerical Methods

- Pp. 275-325 (51)
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Kinetics

- Pp. 327-352 (26)
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In-Core Measurements

- Pp. 353-412 (60)
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Core Design Methods

- Pp. 413-456 (44)
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Nuclear Reactors

- Pp. 457-486 (30)
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Acronyms

- Pp. 487-490 (4)
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Appendix A: Mathematics Fundamentals

- Pp. 491-498 (8)
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Appendix B: Some Thermal Hydraulics Codes

- Pp. 499-500 (2)
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Appendix C: Statistical Physics in Noise Analysis

- Pp. 501-504 (4)
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Appendix D: A Simple Reactor Model

- Pp. 505-507 (3)
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Appendix E: Mathematical Properties of Operators

- Pp. 509-516 (8)
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Appendix F: Symmetries of the Transport Operator

- Pp. 517-530 (14)
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Bibliography

- Pp. 531-540 (10)
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Names

- Pp. 541
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Subjects

- Pp. 543-552 (10)
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