Encyclopedia of Nuclear Energy

1. Introduction to the Encyclopedia of Nuclear Energy - p. iii 2. Section 1 - p. iii 3. Section 1: Fundamentals and History of Development of Nuclear Energy - p. iii 4. Introduction to Fundamentals and History of Development of Nuclear Energy - p. iii 5. What Is the Universe Made of? - p. iii 6. Discovery of Radioactivity - p. iii 7. Discovery of the Quantum Structure of Atoms and Their Nuclei - p. iii 8. Origins of Nuclear Energy - p. iii 9. Radioactive Decay - p. iii 10. Nuclear Fission I - p. iii 11. Nuclear Fission II - p. iii 12. Fissile and Fertile Fuels - p. iii 13. Manhattan Project - p. iii 14. Nuclear Fusion - p. iii 15. Atomic and Hydrogen Bombs - p. iii 16. Phenomenology of Neutron Interactions - p. iii 17. Phenomenology of Gamma Ray and Charged Particles Interactions - p. iii 18. Radiation Sources - p. iii 19. Experimental Tools I: Radiation Detectors - p. iii 20. Experimental Tools II: Particle Accelerators - p. iii 21. Section 2: Commercial Nuclear Power Reactors and their Design - p. iii 22. Commercial Nuclear Power Reactors and Their Design—Introduction - p. iii 23. History of PWR and BWR Development - p. iii 24. Physics of the Fission Chain Reaction in Thermal and Fast Reactors - p. iii 25. Principles of Design and Operation of Nuclear Power Reactors - p. iii 26. Pressurized Water Reactors - p. iii 27. Boiling Water Reactors - p. iii 28. Heavy-Water Reactors - p. iii 29. Commercial Nuclear Power Plant Statistics - p. iii 30. Pros and Cons of Commercial Reactor Designs Part 1: Current Status of Electricity Generation in the World and Selected Countries - p. iii 31. Pros and Cons of Commercial Reactor Designs: Part 2—Current Status and Future Trends in the World Nuclear-Power Industry and Technical Considerations of Nuclear-Power Reactors - p. iii 32. Economics of Nuclear Energy - p. iii 33. Economic Challenges of Nuclear Energy - p. iii 34. Fuel Rod, Fuel Assembly, and Reactivity Control Assembly Design - p. iii 35. Heat Transfer Systems - p. iii 36. Instrumentation and Control Systems of Nuclear Power Plants - p. iii 37. Reactor Operations - p. iii 38. Operational Analysis Methods - p. iii 39. Transient Analysis Methods - p. iii 40. Containment - p. iii 41. Design of the Balance of Plant - p. iii 42. Safety of Nuclear Reactors - p. iii 43. Management of the Nuclear Waste – Via Disposition or Transmutation - p. iii 44. Section 3: Advanced Nuclear Reactor Concepts Under R&D - p. iii 45. Worldwide Status of Advanced Reactors (GEN IV) Research and Technology Development - p. iii 46. Sodium-Cooled Fast Reactors - p. iii 47. The High Temperature Gas-Cooled Reactor - p. iii 48. Lead Cooled Fast Reactors - p. iii 49. Gas Cooled Fast Reactor System (GFR) - p. iii 50. Molten Salt Reactors - p. iii 51. Super-Critical Water-Cooled Reactor (SCWR) - p. iii 52. Advanced Light Water-Cooled Reactor Concepts - p. iii 53. Fluoride-Salt-Cooled High-Temperature Reactors - p. iii 54. Introduction to Breed and Burn Reactors - p. iii 55. Molten Chloride Fast Reactors (MCFRs) - p. iii 56. Traveling Wave Reactor (TWR®) - p. iii 57. CANDLE Reactor Concept - p. iii 58. A Seed-Driven Breed-and-Burn Blanket Core Concept - p. iii 59. Worldwide Status of Small Reactors Research and Technology Development - p. iii 60. Water Cooled Small Modular Reactors (Integral PWR and BWR) - p. iii 61. Floating Nuclear Power Plants With Small Modular Reactors - p. iii 62. Pebble Bed Gas Cooled Reactors - p. iii 63. Heavy Liquid Metal (HLM) Cooled Fast Small Modular Reactors - p. iii 64. Micro-Reactors - p. iii 65. Light Water Reactors (LWR) Fuel Cycle Options - p. iii 66. Advanced Fuel Cycles Identification and Evaluation - p. iii 67. Self-Sustaining Breeding in Advanced Reactors: Characterization of Natural Resources - p. iii 68. Self-Sustaining Breeding in Advanced Reactors: Characterization of Selected Reactors - p. iii 69. Self-Sustaining Breeding in Advanced Reactors: Comparison of Fuel Cycle Performance - p. iii 70. Advanced Modeling and Simulation Methods - p. iii 71. Additive Manufacturing in the Nuclear Reactor Industry - p. iii 72. New Reactor Concepts Deployment Challenges and Opportunities - p. iii 73. Section 4 - p. iii 74. Section 4: Safety, Licensing and Decommissioning of Power Reactors - p. iii 75. Safety, Regulation, and Decommissioning of Commercial Nuclear Power Reactors—Introduction - p. iii 76. Safety Lessons From Two Events Without Core Damage - p. iii 77. The Three Mile Island Unit 2 Accident - p. iii 78. The Chernobyl Nuclear Power Plant Unit-4 Accident - p. iii 79. The Events at Fukushima Daiichi - p. iii 80. Ensuring Safety by Design and Evaluation - p. iii 81. Reactor Protection System - p. iii 82. Engineered Safety Features - p. iii 83. Instrumentation and Control - p. iii 84. Guidance for Operating Within Design Basis Conditions - p. iii 85. Beyond Design Basis Event Considerations - p. iii 86. Safety Evaluations - p. iii 87. Overview of Nuclear Regulation and Regulatory Framework - p. iii 88. U.S. Regulation and Licensing—Historical Perspective - p. iii 89. U.S. Regulations for Commercial Nuclear Power Plants - p. iii 90. U.S. Options for Licensing a New Commercial Power Plant - p. iii 91. Regulation of Two U.S. Non-LWRs—Lessons Learned - p. iii 92. Overview of International Nuclear Safety Regulation and Licensing - p. iii 93. Probabilistic Risk Assessment - p. iii 94. Regulatory Applications of Risk Assessment - p. iii 95. Risk Assessment Insights and Impact - p. iii 96. Nuclear Power Plant Decommissioning - p. iii 97. SAFSTOR Decommissioning Example (Kewaunee) - p. iii 98. DECON Decommissioning Example (Maine Yankee) - p. iii 99. Section 5: The Nuclear Fuel and Fuel Cycle - p. iii 100. Introduction to Fuel Cycle Front End: From Mining Through Utilization - p. iii 101. Uranium Resources - p. iii 102. Uranium Extraction From Seawater Makes Nuclear Power Virtually Renewable - p. iii 103. Unconventional Uranium Resources From Phosphates - p. iii 104. Uranium Conversion and Enrichment - p. iii 105. Fuel Design and Fabrication: Pellet-Type Fuel - p. iii 106. Fuel Design and Fabrication: Fast-Reactor Metal Fuels - p. iii 107. Fuel Design and Fabrication: TRISO Particle Fuel - p. iii 108. Fuel Design and Fabrication: Research Reactor Fuel - p. iii 109. Nuclear Criticality Safety - p. iii 110. Fresh Fuel Properties: Ceramic Compounds - p. iii 111. Zr-Alloyed Metallic Fuel Properties - p. iii 112. Molten Salt Fuels: Properties, Purification, and Corrosion Control - p. iii 113. Irradiation Performance: Light Water Reactor Fuels - p. iii 114. Irradiation Performance: Fast Reactor Fuels - p. iii 115. Irradiation Performance: High-Temperature Gas Reactor Fuels - p. iii 116. Irradiation Performance: Research Reactor Fuels - p. iii 117. Section 6: The Nuclear Waste and its Disposal - p. iii 118. Key Characteristics of Used Nuclear Fuel - p. iii 119. Fuel Storage (New Fuel/Used Fuel Pool) - p. iii 120. The Chemical Basis for Separating Recycling Materials by Hydro-Processes - p. iii 121. The Chemical Basis for Separating Recycling Materials by Pyro-Processes - p. iii 122. The Current Industrial Mono-Recycling of U and Pu: Reprocessing Step - p. iii 123. The Current Industrial Mono-Recycling of U and Pu: Recycling Step - p. iii 124. Routes for Pu Multi-recycling - p. iii 125. The Adaptation of Recycling Processes to Pu-Multi Recycling - p. iii 126. Effluent Decontamination - p. iii 127. ILW conditioning and performance - p. iii 128. HLW Conditioning and Long-Term Performance - p. iii 129. Spent nuclear fuel long term behavior and performance - p. iii 130. The Concept of Geological Disposal of Highly Radioactive Nuclear Waste - p. iii 131. Radionuclide Migration in the Context of High-Level Nuclear Waste Management - p. iii 132. Main Repository Projects Worldwide - p. iii 133. Actinide Immobilization in Dedicated Wasteforms: An Alternative Pathway for the Long-Term Management of Existing Actinide Stockpiles - p. iii 134. Potential Fuel Cycle Back-End for Thorium Fuel Cycle - p. iii 135. Assessment of the Relative Environmental Footprint of Nuclear Energy and Its Fuel Cycle - p. iii 136. Social Acceptability of Geologic Disposal - p. iii 137. Section 7: Radiation Protection - p. iii 138. Radiation Protection – Introduction - p. iii 139. Ionizing Radiation: Discovery and Dose Quantities - p. iii 140. Fundamentals of Health Physics - p. iii 141. Natural and Man-Made Sources of Radiation - p. iii 142. Source Terms for Nuclear Reactors Operations, Accidents, and Waste - p. iii 143. External Dosimetry - p. iii 144. Internal Dosimetry - p. iii 145. Instrumentation and Practices for Radiological Assessments - p. iii 146. Emergency Response - p. iii 147. Standards to Control Radiation Exposures of Workers and the Public - p. iii 148. Risk Tradeoff Analysis - p. iii 149. Computer Codes for Determining Acceptable Levels of Contamination - p. iii 150. Characterization and Release of Contaminated Sites - p. iii 151. Radiological Control Practices - p. iii 152. Radiation Shielding Methods - p. iii 153. Shielding Against Galactic and Solar Radiation in Space - p. iii 154. Health Effects and Radiation Biology - p. iii 155. Estimation of Health Risks From Exposure to Ionizing Radiation - p. iii 156. Drones for Radiological Assessment - p. iii 157. An Illustrative Example of Microdosimetry—Boron Neutron Capture Therapy for Cancer - p. iii 158. Radiation Protection: Glossary of Terms - p. iii 159. Section 8 - p. iii 160. Section 8: Non-Electric Applications of Terrestrial Nuclear Reactors - p. iii 161. Introduction to Nonelectric Applications of Nuclear Energy - p. iii 162. District Heating and Nuclear Power - p. iii 163. Nuclear Driven Water Desalination - p. iii 164. Nuclear-Supported Electrification of the Transportation Sector - p. iii 165. Heat Pumps Driven by Zero-Carbon Electricity - p. iii 166. Coupling Heat Storage to Base-Load Nuclear Reactors for Variable Heat, Electricity and Hydrogen - p. iii 167. Process Heat for Chemical Industry - p. iii 168. Industrial Processes for Grid Stabilization - p. iii 169. Thermochemical Hydrogen Production - p. iii 170. High Temperature Steam Electrolysis - p. iii 171. Synthetic Hydrocarbon Fuels From H2 and Captured CO2 - p. iii 172. Ammonia Synthesis - p. iii 173. Hydrogen-Based Flash Ironmaking Technology (HyFIT): A Novel Green Ironmaking Technology With Low Energy Consumption - p. iii 174. Calcination - p. iii 175. Marine Propulsion - p. iii 176. Section 9: Nuclear Power for Space and Propulsion - p. iii 177. Introduction to Space Nuclear Power and Propulsion - p. iii 178. Radioisotope Power: Benefits and Challenges - p. iii 179. Radioisotope Power: Historical Review - p. iii 180. Radioisotope Power: Technology Options - p. iii 181. Space Fission Power: Benefits and Challenges - p. iii 182. Space Fission Power: Historical Review - p. iii 183. Space Fission Power: Technology Options – Reactor Core - p. iii 184. Space Fission Power: Technology Options—Heat Transport - p. iii 185. Space Fission Power: Technology Options—Radiation Shielding - p. iii 186. Space Fission Power: Kilopower and KRUSTY - p. iii 187. Nuclear Thermal Propulsion: Benefits and Challenges - p. iii 188. The History of Nuclear Thermal Rocket Development - p. iii 189. Nuclear Thermal Propulsion: Technology Options - p. iii 190. Nuclear Electric Propulsion for Rapid Transportation Within the Solar System - p. iii 191. Advanced Propulsion: Pulsed, Fusion, Antimatter and Breakthrough Physics - p. iii 192. Space Nuclear Power Safety and Safeguards - p. iii 193. Section 10: Nuclear Fusion R&D - p. iii 194. Nuclear Fusion – Introduction and Overview - p. iii 195. Magnetic Confinement Fusion—Principles - p. iii 196. Magnetic Confinement Fusion Concepts/Configurations - p. iii 197. Magnetic Confinement Fusion—Plasma Theory: Kinetic and Fluid Analysis - p. iii 198. Magnetic Confinement Fusion—Plasma Theory: Transport and Confinement - p. iii 199. Magnetic-Confinement Fusion—Plasma Theory: Tokamak Magnetohydrodynamic Equilibrium and Stability - p. iii 200. Magnetic Confinement Fusion—Plasma Theory: Energetic Particle Physics - p. iii 201. Magnetic Confinement Fusion—Plasma Theory: Heating and Current Drive - p. iii 202. Magnetic Confinement Fusion—Experimental Physics: Tokamak - p. iii 203. Magnetic Confinement Fusion—Experimental Physics: Stellarators - p. iii 204. Magnetic Confinement Fusion—Experimental Physics: Reversed Field Pinches - p. iii 205. Magnetic Confinement Fusion—Technology: Fusion Core - p. iii 206. Magnetic Confinement Fusion Technology: “Plasma Engineering” - p. iii 207. Fusion—Reactor Materials - p. iii 208. Magnetic Confinement Fusion—Reactor Blanket Technologies - p. iii 209. Magnetic Confinement Fusion—Development Facilities - p. iii 210. Magnetic Confinement Fusion—Power Plant Concepts - p. iii 211. Inertial Confinement Fusion – Physics Principles - p. iii 212. Inertial Confinement Fusion – Key Elements of Plasma Physics - p. iii 213. Inertial Confinement Fusion—Experimental Physics: Laser Drive - p. iii 214. Inertial Confinement Fusion—Experimental Physics: Heavy Ion Beam Drive - p. iii 215. Inertial Confinement Fusion - Experimental Physics: Z-Pinch and Magnetized Liner Inertial Fusion - p. iii 216. Overview of IFE Key Power Plant Technologies - p. iii 217. Inertial Confinement Fusion—Major Facilities - p. iii 218. Inertial Confinement Fusion Power Plants - p. iii 219. Fusion—Safety and Environmental Considerations - p. iii 220. Section 11 - p. iii 221. Section 11: Research Reactors - p. iii 222. An Introduction to Research Reactors - p. iii 223. Applications of Research Reactors - p. iii 224. Historical Survey of Test Reactor Programs at INL Over 70 Years - p. iii 225. Historical Survey of Fast Test Reactors - p. iii 226. The Transient Reactor Test (TREAT) Facility at the Idaho National Laboratory - p. iii 227. The Advanced Test Reactor - p. iii 228. High Flux Isotope Reactor (HFIR) - p. iii 229. The National Bureau of Standards Reactor at the NIST Center for Neutron Research - p. iii 230. The Annular Core Research Reactor (ACRR) Description and Capabilities - p. iii 231. MIR.M1 (100 MW) - p. iii 232. The BR2 Reactor: Short History, Characteristics and Utilization - p. iii 233. The Jules Horowitz Reactor - p. iii 234. FRM II (20 MW Germany) - p. iii 235. MARIA Research Reactor - p. iii 236. HANARO - p. iii 237. Dhruva—A 100 MWth Indian Research Reactor - p. iii 238. The OPAL Research Reactor - p. iii 239. University of Missouri Research Reactor - p. iii 240. MIT Research Reactor (MITR-II) - p. iii 241. North Carolina State University PULSTAR Reactor - p. iii 242. TRIGA® Reactors: A Unique Approach in Research Reactor Fuel and Design - p. iii 243. Accelerator Driven Subcritical Systems - p. iii 244. Research Reactor Conversion to Low Enriched Uranium (LEU) Fuel - p. iii 245. Section 12: Medical, Industrial and Agricultural Applications of Nuclear Technology - p. iii 246. Harnessing Nuclear Radiation - p. iii 247. Medicine: Sterilization - p. iii 248. Medicine: Radionuclides Used in Nuclear Medicine - p. iii 249. Medicine: Radiopharmaceuticals and Their Use in Nuclear Medicine - p. iii 250. Medicine: New Drug Developments - p. iii 251. Medicine: Therapeutic and Other Applications Using Sealed Radiation Sources - p. iii 252. Agriculture: Improving Crop Production - p. iii 253. Agriculture: Improving Livestock Production - p. iii 254. Agriculture: Electron Beam Irradiation Technology Applications in the Food Industry - p. iii 255. Modern Industry: Diagnostics and Process Control - p. iii 256. Modern Industry: Gamma Methods for Materials Testing and Inspection - p. iii 257. Modern Industry: Neutron Basic Interactions, Sources and Detectors for Materials Testing and Inspection - p. iii 258. Modern Industry: Application of Neutrons for Materials Testing and Inspection - p. iii 259. Modern Industry—Development of New Materials - p. iii 260. Modern Industry: Non-nuclear Energy Applications - p. iii 261. Modern Industry: Personal Care, Conveniences, and Safety - p. iii 262. Environmental Protection: Managing Fresh Water Resources - p. iii 263. Environmental Protection: The Oceans—Formation and Global Climate Change - p. iii 264. Environmental Protection: The Oceans—Implications of Manmade Radiation - p. iii 265. Environmental Protection: Reducing Environmental Pollution - p. iii 266. Public Safety: Fighting Crime and Terrorism; Border Security - p. iii 267. Public Safety and Security: Emerging Inspection Technologies—Active Interrogation for Nuclear Materials - p. iii 268. Public Safety: High Radiation Sources and Alternative Technologies - p. iii 269. Public Safety and Security: Nuclear Forensics - p. iii 270. Cultural Heritage Preservation - p. iii 271. Global Market for Radiation Applications - p. iii 272. Section 13: Social Issues of Nuclear Energy - p. iii 273. Introduction to the Social Issues of Nuclear Energy - p. iii 274. Public Images of Nuclear Energy - p. iii 275. Factors Affecting Public Opinion of Nuclear Energy in the United States - p. iii 276. Relative Nuclear Energy Health Hazards and Popular Acceptance - p. iii 277. Securing Nuclear Power’s Contribution to Decarbonization - p. iii 278. The Environmentalist’s Dilemma - p. iii 279. Mankind Benefits From Nuclear Energy and Radiation - p. iii 280. Origins and Resources of Uranium and Thorium - p. iii 281. Economics of Nuclear Power versus Other Energy Sources - p. iii 282. How Innovative New Reactors Could Improve Public Acceptance - p. iii 283. Impact of Small Modular Reactors on the Acceptance of Nuclear Power by the Public, Investors, and Owners - p. iii 284. Floating Nuclear Plants to Improve Economics, Safety, Siting, and Proliferation Resistance - p. iii 285. Microreactors for Decentralized Power Sources - p. iii 286. Non-Proliferation Aspects of Nuclear Energy - p. iii 287. The Case for International Fuel Cycle Centers to Reduce Proliferation Risk - p. iii 288. Nuclear Waste Can Be Reduced by Recycling and Transmutation - p. iii 289. Nuclear Waste Can Be Disposed of Safely - p. iii 290. International Nuclear Waste Disposal Centers - p. iii 291. Index - p. iii 292. Author Index - p. iii