Progress in Nuclear Energy

Author: Williams   M. M. R.;Sher   R.  

Publisher: Elsevier Science‎

Publication year: 2013

E-ISBN: 9781483103365

P-ISBN(Paperback): 9780080271156

P-ISBN(Hardback):  9780080271156

Subject:

Language: ENG

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Description

Progress in Nuclear Energy, Volume 5 covers the significant advances in several aspects of nuclear energy field. This book is composed six chapters that describe the progress in nuclear and gas-cooled reactors.

The introductory chapter deals with the development and evolution of decay heat estimates and decay heat Standards, and illustrates the use of these estimates through comparison of both the actinide and fission product decay heat levels from typical fuel samples in a variety of reactor systems. The succeeding chapters present different practical methods for handling resonance absorption problem in the case of thermal reactor lattices and review the physics of the different noise phenomena. These topics are followed by discussions of the developed methodology for the description of breeding, conversion, long-term fuel logistics, and related subjects derived from the detailed mathematical description of the fuel cycle. The concluding chapters consider the historical development of heat transfer surfaces for gas-cooled reactors. These chapters also provide a complete set of differential nuclear data on the three technologically important americium isotopes, 241Am, 242Am, and 243Am, suitable for incorporation into the computer-based U.K. Nuclear Data Library.

This book will prove useful to nuclear physicists and nuclear energy scientists and researchers.

Chapter

3. CONFIRMATION OF SUMMATION CALCULATIONS

4. THE EFFECT OF NEUTRON ABSORPTION IN FISSION PRODUCTS

5. UNCERTAINTIES IN DECAY HEAT SUMMATION CALCULATIONS

6. THE DEVELOPMENT AND USE OF DECAY HEAT STANDARDS

7. COMPARISONS OF DECAY HEAT PROPERTIES

8. CONCLUSIONS

REFERENCES

CHAPTER 2. RESONANCE ABSORPTION CALCULATIONS IN THERMAL REACTORS

1. INTRODUCTION

2. RESONANCE REACTION RATES, GROUP AVERAGE RESONANCE CROSS-SECTIONS,EFFECTIVE RESONANCE INTEGRALS

3. CALCULATION OF EFFECTIVE RESONANCE INTEGRALS

4. DIRECT CALCULATIONS OF RESONANCE REACTION RATES USING RESONANCE PARAMETERS OR TABULATED CROSS SECTIONS

5. CONCLUSION

REFERENCES

APPENDIX A

APPENDIX B

APPENDIX C

REFERENCES

CHAPTER 3. NOISE INVESTIGATIONS IN BOILING-WATER AND PRESSURIZED-WATER REACTORS

1. INTRODUCTION

2. POINT KINETIC BEHAVIOUR AND SPACE DEPENDENCE OF NEUTRON NOISE

3. NOISE INVESTIGATIONS IN BOILING-WATER REACTORS

4. NOISE INVESTIGATIONS IN PRESSURIZED -WATER REACTORS

REFERENCES

CHAPTER 4. FAST REACTOR BURNUP AND BREEDING CALCULATION METHODOLOGY

NOMENCLATURE

PART 1: FUEL CYCLE ANALYSIS

1. MATHEMATICAL DESCRIPTION OF THE FUEL CYCLE

2. NUMERICAL SOLUTION OF FUEL CYCLE PROBLEMS

3. TYPICAL RESULTS OF THE DISCONTINUOUS FUEL-CYCLE DESCRIPTION

4. INTEGRATED FUEL CYCLE DESCRIPTION

PART 2: DESCRIPTION OF BREEDING

1. INTUITIVE VERSUS MATHEMATICAL DESCRIPTIONS

2. HISTORICAL DEVELOPMENT OF BREEDING QUANTIFICATION CONCEPTS

3. ASYMPTOTIC FUEL GROWTH

4. ISOTOPIC BREEDING WORTH

5. TRANSITORY FUEL GROWTH

6. NUMERICAL RESULTS

7. DESCRIPTION OF BREEDING WITH THREE INTEGRAL CONCEPTS

8. DELAYED FUEL GROWTH

9. SYMBIOTIC AND NEGATIVE-GROWTH-RATE SYSTEMS

10. FUEL LOGISTICS

11. BREEDING RATIO, BREEDING GAIN AND CONVERSION RATIO

SUMMARY

REFERENCES

CHAPTER 5. THE HISTORICAL DEVELOPMENT OF HEAT TRANSFER SURFACES FOR GAS-COOLED REACTORS ANALYSED WITH A SIMPLE CRITERION

1. HISTORICAL INTRODUCTION

2. A NOTE ON EQUIVALENT DIAMETERS

3. CRITERIA FOR OPTIMIZATION

4. OPTIMIZATION OF TYPICAL HEAT TRANSFER SURFACES

5. COMPARISON OF THREE TYPES OF FIN

APPENDIX

REFERENCES

CHAPTER 6. EVALUATION OF DIFFERENTIAL NUCLEAR DATA FOR AMERICIUM ISOTOPES PART I: 241 Am

1. INTRODUCTION

2. HALF-LIFE AND DECAY SCHEME DATA

3. CROSS-SECTIONS OF 241 Am

4. COMPARISON WITH OTHER EVALUATIONS

5. ANGULAR DISTRIBUTIONS AND SECONDARY ENERGIES

6. UNCERTAINTIES IN THE EVALUATED DATA

REFERENCES

SUBJECT INDEX

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