Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations.
Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions.
Cover image: Kaiga Atomic Power Station Units 1 – 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India.
1. Chapter 1. Introduction - p. 1 2. Chapter 2. Nuclear data - p. 87 3. Abstract - p. 87 4. 2.1 Introduction: Nuclear data and its importance - p. 87 5. 2.2 Nuclear data production - p. 91 6. 2.3 Nuclear data evaluation - p. 106 7. 2.4 Nuclear data processing - p. 125 8. 2.5 Summary - p. 151 9. 2.6 Exercise problems - p. 152 10. References - p. 153 11. Further reading - p. 154 12. Chapter 3. Types of nuclear reactors - p. 155 13. Chapter 4. Homogeneous reactor and neutron diffusion equation - p. 193 14. Abstract - p. 193 15. 4.1 Introduction - p. 193 16. 4.2 Neutron density and flux - p. 194 17. 4.3 Neutron continuity equation - p. 195 18. 4.4 Transport cross-section - p. 197 19. 4.5 Fick's law of neutron diffusion - p. 199 20. 4.6 Diffusion equation - p. 205 21. 4.7 Neutron diffusion in nonmultiplying media - p. 210 22. 4.8 Neutron diffusion in a multiplying media - p. 215 23. 4.9 Reflected infinite slab reactor - p. 225 24. 4.10 Neutron life cycle in a thermal reactor - p. 233 25. 4.11 Slowing down equation - p. 232 26. 4.12 Neutron thermalization - p. 242 27. 4.13 Two-group diffusion theory - p. 249 28. 4.14 Multigroup diffusion equation - p. 252 29. 4.15 Numerical solution of the diffusion equation in 1-D slab geometry - p. 254 30. 4.16 Summary and more topics of interest - p. 258 31. 4.17 Exercise problems - p. 258 32. References - p. 261 33. Further reading - p. 262 34. Chapter 5. Methods of solving neutron transport equation - p. 263 35. Abstract - p. 263 36. 5.1 Introduction - p. 264 37. 5.2 Assumptions in the neutron transport theory - p. 264 38. 5.3 Neutron-nucleus interaction cross-sections - p. 264 39. 5.4 The neutron transport equation - p. 265 40. 5.5 Solution to the neutron transport equation - p. 272 41. 5.6 Numerical solution to the neutron transport equation - p. 277 42. 5.7 The synthetic acceleration schemes - p. 282 43. 5.8 The integral form of transport equation - p. 286 44. 5.9 Solution to the integral transport equation - p. 289 45. 5.10 Method of characteristics approach - p. 309 46. 5.11 Monte Carlo neutron transport - p. 318 47. 5.12 More topics of interest - p. 327 48. 5.13 Exercise problems - p. 327 49. References - p. 329 50. Chapter 6. Fuel burnup, fuel management, and fuel cycle physics - p. 331 51. Chapter 7. Nuclear reactor kinetics - p. 373 52. Abstract - p. 373 53. 7.1 Introduction - p. 373 54. 7.2 Definition of important kinetics parameters - p. 374 55. 7.3 Prompt and delayed neutrons - p. 375 56. 7.4 The point kinetics equations - p. 380 57. 7.5 Kinetics of a subcritical reactor - p. 392 58. 7.6 Numerical solution of point kinetics equations - p. 397 59. 7.7 Reactivity feedback in nuclear reactors - p. 400 60. 7.8 Long irradiation reactivity effects in reactors - p. 405 61. 7.9 Reactor stability analysis - p. 409 62. 7.10 Neutronic coupling in a reactor - p. 427 63. 7.11 Xenon oscillations - p. 431 64. 7.12 Space time kinetics - p. 436 65. 7.13 Summary - p. 444 66. A.1 Annexure - p. 444 67. 7.14 Exercise problems - p. 446 68. References - p. 447 69. Chapter 8. Nuclear reactor safety - p. 490 70. Chapter 9. Design methods and computer codes - p. 511 71. Chapter 10. Experimental and operational reactor physics - p. 571 72. Chapter 11. Radiation safety and radiation shielding design - p. 670 73. Chapter 12. Nuclear reactors of the future - p. 695 74. Index - p. 747
Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations.
Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions.
Cover image: Kaiga Atomic Power Station Units 1 – 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India.
1. Chapter 1. Introduction - p. 1 2. Chapter 2. Nuclear data - p. 87 3. Abstract - p. 87 4. 2.1 Introduction: Nuclear data and its importance - p. 87 5. 2.2 Nuclear data production - p. 91 6. 2.3 Nuclear data evaluation - p. 106 7. 2.4 Nuclear data processing - p. 125 8. 2.5 Summary - p. 151 9. 2.6 Exercise problems - p. 152 10. References - p. 153 11. Further reading - p. 154 12. Chapter 3. Types of nuclear reactors - p. 155 13. Chapter 4. Homogeneous reactor and neutron diffusion equation - p. 193 14. Abstract - p. 193 15. 4.1 Introduction - p. 193 16. 4.2 Neutron density and flux - p. 194 17. 4.3 Neutron continuity equation - p. 195 18. 4.4 Transport cross-section - p. 197 19. 4.5 Fick's law of neutron diffusion - p. 199 20. 4.6 Diffusion equation - p. 205 21. 4.7 Neutron diffusion in nonmultiplying media - p. 210 22. 4.8 Neutron diffusion in a multiplying media - p. 215 23. 4.9 Reflected infinite slab reactor - p. 225 24. 4.10 Neutron life cycle in a thermal reactor - p. 233 25. 4.11 Slowing down equation - p. 232 26. 4.12 Neutron thermalization - p. 242 27. 4.13 Two-group diffusion theory - p. 249 28. 4.14 Multigroup diffusion equation - p. 252 29. 4.15 Numerical solution of the diffusion equation in 1-D slab geometry - p. 254 30. 4.16 Summary and more topics of interest - p. 258 31. 4.17 Exercise problems - p. 258 32. References - p. 261 33. Further reading - p. 262 34. Chapter 5. Methods of solving neutron transport equation - p. 263 35. Abstract - p. 263 36. 5.1 Introduction - p. 264 37. 5.2 Assumptions in the neutron transport theory - p. 264 38. 5.3 Neutron-nucleus interaction cross-sections - p. 264 39. 5.4 The neutron transport equation - p. 265 40. 5.5 Solution to the neutron transport equation - p. 272 41. 5.6 Numerical solution to the neutron transport equation - p. 277 42. 5.7 The synthetic acceleration schemes - p. 282 43. 5.8 The integral form of transport equation - p. 286 44. 5.9 Solution to the integral transport equation - p. 289 45. 5.10 Method of characteristics approach - p. 309 46. 5.11 Monte Carlo neutron transport - p. 318 47. 5.12 More topics of interest - p. 327 48. 5.13 Exercise problems - p. 327 49. References - p. 329 50. Chapter 6. Fuel burnup, fuel management, and fuel cycle physics - p. 331 51. Chapter 7. Nuclear reactor kinetics - p. 373 52. Abstract - p. 373 53. 7.1 Introduction - p. 373 54. 7.2 Definition of important kinetics parameters - p. 374 55. 7.3 Prompt and delayed neutrons - p. 375 56. 7.4 The point kinetics equations - p. 380 57. 7.5 Kinetics of a subcritical reactor - p. 392 58. 7.6 Numerical solution of point kinetics equations - p. 397 59. 7.7 Reactivity feedback in nuclear reactors - p. 400 60. 7.8 Long irradiation reactivity effects in reactors - p. 405 61. 7.9 Reactor stability analysis - p. 409 62. 7.10 Neutronic coupling in a reactor - p. 427 63. 7.11 Xenon oscillations - p. 431 64. 7.12 Space time kinetics - p. 436 65. 7.13 Summary - p. 444 66. A.1 Annexure - p. 444 67. 7.14 Exercise problems - p. 446 68. References - p. 447 69. Chapter 8. Nuclear reactor safety - p. 490 70. Chapter 9. Design methods and computer codes - p. 511 71. Chapter 10. Experimental and operational reactor physics - p. 571 72. Chapter 11. Radiation safety and radiation shielding design - p. 670 73. Chapter 12. Nuclear reactors of the future - p. 695 74. Index - p. 747
