| Preface to Second Edition |
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xi | |
| Preface to First Edition |
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xiii | |
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The Earth and Nuclear Power: Sources and Resources |
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1 | (27) |
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1 | (8) |
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2 | (3) |
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5 | (1) |
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Energy Conversion Process |
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6 | (3) |
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Earth's Internal Heat Generation |
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9 | (6) |
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15 | (2) |
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17 | (5) |
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22 | (6) |
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24 | (1) |
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25 | (1) |
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26 | (2) |
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28 | (34) |
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28 | (1) |
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28 | (6) |
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Basic Components of a Nuclear Reactor |
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34 | (3) |
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37 | (18) |
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Natural Uranium Graphite-Moderated (Magnox) Reactors |
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37 | (3) |
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Advanced Gas-Cooled Reactors |
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40 | (3) |
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Pressurized-Water Reactors |
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43 | (3) |
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46 | (2) |
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Natural Uranium Heavy Water-Moderated and-Cooled Reactors |
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48 | (2) |
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Boiling-Water, Graphite-Moderated Direct-Cycle Reactor (RBMK) |
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50 | (5) |
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55 | (7) |
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Liquid Metal-Cooled Fast Breeder Reactors |
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55 | (5) |
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60 | (1) |
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61 | (1) |
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62 | (30) |
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62 | (1) |
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General Features of a Reactor Coolant |
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62 | (2) |
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Principles of Heat Transfer |
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64 | (8) |
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72 | (3) |
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72 | (1) |
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73 | (1) |
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74 | (1) |
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75 | (1) |
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75 | (5) |
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75 | (2) |
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77 | (1) |
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77 | (1) |
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78 | (1) |
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78 | (2) |
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80 | (2) |
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81 | (1) |
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81 | (1) |
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Alternative Forms of Reactor Coolant Circuits |
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82 | (10) |
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83 | (1) |
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84 | (1) |
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85 | (2) |
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87 | (1) |
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88 | (1) |
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88 | (3) |
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91 | (1) |
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92 | (50) |
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92 | (7) |
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99 | (2) |
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Pressurized-Water Reactor |
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101 | (22) |
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Operating States of the PWR |
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101 | (6) |
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Energy Balances in the PWR under Fault Conditions |
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107 | (2) |
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The Large-Break LOCA in the PWR |
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109 | (7) |
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116 | (7) |
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123 | (1) |
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123 | (5) |
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Large-Break LOCA in a BWR (the Design Basis Accident) |
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124 | (2) |
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Small-Break LOCAs in BWRs |
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126 | (2) |
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128 | (2) |
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130 | (4) |
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Design Basis Accident for the AGR: Depressurization Fault |
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133 | (1) |
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Sodium-Cooled Fast Reactor |
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134 | (8) |
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136 | (1) |
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136 | (5) |
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141 | (1) |
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Loss-Of-Cooling Accidents: Some Examples |
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142 | (66) |
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142 | (1) |
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Incidents in Light Water--Cooled Reactors |
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143 | (41) |
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143 | (1) |
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144 | (1) |
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145 | (1) |
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The Three Mile Island (TMI) Accident |
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146 | (14) |
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160 | (1) |
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161 | (3) |
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The Serious Accident at Chernobyl |
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164 | (20) |
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Heavy Water--Moderated Reactors |
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184 | (4) |
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184 | (2) |
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The Core-Damage Incident at Lucens |
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186 | (2) |
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188 | (6) |
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188 | (2) |
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The Fuel Meltdown at St. Laurent |
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190 | (1) |
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Seawater Ingress in the Hunterston BAGR Station |
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191 | (2) |
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Fuel Damage during Charging at the Hinkley Point BAGR |
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193 | (1) |
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Liquid Metal--Cooled Fast Reactors |
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194 | (3) |
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The EBR-1 Meltdown Accident |
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194 | (2) |
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Fuel Melting Incident at the Enrico Fermi 1 Fast Breeder Reactor |
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196 | (1) |
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The International Nuclear Event Scale (INES) |
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197 | (11) |
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202 | (1) |
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202 | (5) |
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207 | (1) |
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Postulated Severe Accidents |
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208 | (26) |
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208 | (1) |
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Postulated Severe Accidents in Water-Cooled Reactors |
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209 | (8) |
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209 | (2) |
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Challenges to the Reactor Pressure Vessel |
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211 | (2) |
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Challenges to the Reactor Containment |
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213 | (3) |
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Mitigating the Consequences of Severe Accidents |
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216 | (1) |
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Specific Phenomena relating to Severe Accidents |
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217 | (8) |
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Fuel-Coolant Interactions:-``Steam Explosions'' |
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217 | (2) |
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Debris Beds and Their Cooling |
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219 | (2) |
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Hydrogen Formation: Burning and Explosions |
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221 | (2) |
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Containment Basement Melt-Through and Failure |
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223 | (2) |
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Severe Accidents in Other Reactor Types |
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225 | (3) |
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Fission Product Dispersion following containment Failure |
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228 | (6) |
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228 | (1) |
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229 | (4) |
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233 | (1) |
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Cooling during Fuel Removal and Processing |
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234 | (23) |
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234 | (2) |
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236 | (7) |
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Refueling of Gas-Cooled Reactors |
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236 | (2) |
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Refueling of CANDU Reactors |
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238 | (3) |
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Refueling of Light-Water Reactors |
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241 | (1) |
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Refueling of Liquid Metal--Cooled Fast Breeder Reactors |
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242 | (1) |
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Spent Fuel Storage and Transport |
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243 | (5) |
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248 | (9) |
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252 | (2) |
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254 | (2) |
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256 | (1) |
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Cooling and Disposing of the Waste |
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257 | (24) |
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257 | (1) |
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Classification of Waste Products |
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257 | (2) |
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Fission Products and Their Biological Significance |
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259 | (3) |
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Options for Nuclear Waste Disposal |
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262 | (2) |
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Long-Term Storage and Disposal of Spent Nuclear Fuel |
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264 | (5) |
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Ultimate Disposal in Salt Deposits |
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267 | (1) |
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267 | (2) |
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Storage and Disposal of Fission Products from Reprocessing Plants |
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269 | (4) |
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Disposal of Other Materials |
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273 | (8) |
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275 | (1) |
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275 | (5) |
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280 | (1) |
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Fusion Energy: Prospect for the Future |
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281 | (18) |
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281 | (1) |
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282 | (2) |
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284 | (2) |
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Current Technical Position |
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286 | (7) |
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293 | (6) |
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294 | (1) |
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294 | (3) |
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297 | (2) |
| Index |
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299 | |