Plutonium and Highly Enriched Uranium 1996 World Inventories, Capabilities, and Policies
, by Albright, David; Berkhout, Frans; Walker, William- ISBN: 9780198280095 | 0198280092
- Cover: Hardcover
- Copyright: 5/29/1997
Preface | xv | (1) | |||
Acknowledgements | xvi | (1) | |||
Glossary | xvii | (11) | |||
Abbreviations, acronyms and conventions | xxviii | ||||
Part I. Introduction | 3 | (26) | |||
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3 | (9) | |||
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3 | (1) | |||
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4 | (2) | |||
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6 | (2) | |||
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8 | (1) | |||
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9 | (1) | |||
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10 | (2) | |||
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12 | (17) | |||
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12 | (1) | |||
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12 | (6) | |||
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18 | (2) | |||
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20 | (3) | |||
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23 | (6) | |||
Part II. Military inventories in the nuclear weapon states | 29 | (104) | |||
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29 | (50) | |||
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29 | (1) | |||
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30 | (3) | |||
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33 | (4) | |||
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37 | (13) | |||
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50 | (9) | |||
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59 | (7) | |||
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66 | (10) | |||
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76 | ||||
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32 | (6) | |||
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38 | (2) | |||
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40 | (2) | |||
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42 | (3) | |||
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45 | (1) | |||
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46 | (1) | |||
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47 | (1) | |||
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48 | (1) | |||
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49 | (5) | |||
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54 | (3) | |||
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57 | (1) | |||
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58 | (7) | |||
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65 | (3) | |||
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68 | ||||
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30 | (11) | |||
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41 | (3) | |||
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44 | (35) | |||
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79 | (54) | |||
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79 | (1) | |||
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79 | (2) | |||
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81 | (13) | |||
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94 | (22) | |||
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116 | (5) | |||
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121 | (5) | |||
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126 | ||||
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80 | (5) | |||
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85 | (6) | |||
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91 | (1) | |||
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92 | (11) | |||
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103 | (3) | |||
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106 | (6) | |||
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112 | (4) | |||
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116 | (4) | |||
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120 | ||||
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82 | (26) | |||
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108 | (11) | |||
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109 | (1) | |||
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110 | (23) | |||
Part III. Principal civil inventories | 133 | (124) | |||
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133 | (15) | |||
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133 | (2) | |||
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135 | (1) | |||
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136 | (2) | |||
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138 | (3) | |||
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141 | (6) | |||
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147 | ||||
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136 | (4) | |||
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140 | (2) | |||
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142 | (1) | |||
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143 | (11) | |||
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134 | (1) | |||
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135 | (2) | |||
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137 | (1) | |||
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138 | (6) | |||
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144 | (1) | |||
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145 | (1) | |||
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146 | (2) | |||
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148 | (45) | |||
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148 | (2) | |||
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150 | (5) | |||
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155 | (1) | |||
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155 | (2) | |||
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157 | (26) | |||
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183 | (7) | |||
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190 | (2) | |||
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192 | ||||
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154 | (2) | |||
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156 | (4) | |||
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160 | (2) | |||
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162 | (6) | |||
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168 | (4) | |||
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172 | (2) | |||
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174 | (10) | |||
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184 | (4) | |||
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188 | (1) | |||
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189 | (1) | |||
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190 | (1) | |||
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191 | ||||
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158 | (5) | |||
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163 | (1) | |||
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166 | (1) | |||
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167 | (2) | |||
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169 | (9) | |||
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178 | (1) | |||
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187 | (6) | |||
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193 | (45) | |||
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193 | (1) | |||
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194 | (1) | |||
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195 | (2) | |||
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197 | (12) | |||
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209 | (3) | |||
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212 | (11) | |||
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223 | (6) | |||
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229 | (8) | |||
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237 | ||||
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196 | (1) | |||
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197 | (8) | |||
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205 | (4) | |||
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209 | (14) | |||
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223 | (1) | |||
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224 | (3) | |||
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227 | (2) | |||
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229 | (1) | |||
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230 | (3) | |||
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233 | (2) | |||
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235 | ||||
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213 | (3) | |||
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216 | (2) | |||
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218 | (8) | |||
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226 | (6) | |||
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232 | (2) | |||
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234 | (2) | |||
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236 | (2) | |||
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238 | (19) | |||
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238 | (1) | |||
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239 | (2) | |||
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241 | (1) | |||
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242 | (3) | |||
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245 | (3) | |||
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248 | (5) | |||
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253 | ||||
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248 | (1) | |||
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249 | (1) | |||
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250 | (1) | |||
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251 | (6) | |||
Part IV. Material inventories and production capabilities in the threshold states | 257 | (138) | |||
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257 | (25) | |||
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257 | (7) | |||
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264 | (7) | |||
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271 | ||||
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262 | (1) | |||
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263 | (6) | |||
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269 | (8) | |||
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277 | (3) | |||
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280 | (2) | |||
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282 | (27) | |||
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282 | (1) | |||
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282 | (1) | |||
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283 | (5) | |||
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288 | (7) | |||
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295 | (8) | |||
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303 | (3) | |||
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306 | (1) | |||
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307 | (1) | |||
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307 | (2) | |||
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309 | (42) | |||
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309 | (2) | |||
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311 | (2) | |||
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313 | (4) | |||
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317 | (24) | |||
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341 | (1) | |||
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342 | (2) | |||
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344 | (5) | |||
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349 | ||||
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320 | (2) | |||
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322 | (1) | |||
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323 | (15) | |||
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338 | (3) | |||
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341 | (4) | |||
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345 | ||||
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316 | (35) | |||
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351 | (18) | |||
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351 | (1) | |||
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352 | (11) | |||
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363 | (2) | |||
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365 | (1) | |||
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366 | (3) | |||
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369 | (26) | |||
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369 | (1) | |||
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369 | (8) | |||
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377 | (10) | |||
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387 | (8) | |||
Part V. Conclusions | 395 | (66) | |||
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395 | (21) | |||
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395 | (1) | |||
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395 | (2) | |||
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397 | (1) | |||
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398 | (3) | |||
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401 | (3) | |||
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404 | (2) | |||
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406 | (5) | |||
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411 | ||||
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397 | (1) | |||
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398 | (1) | |||
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399 | (1) | |||
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400 | (2) | |||
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402 | (1) | |||
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402 | (2) | |||
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404 | (1) | |||
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405 | (3) | |||
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408 | (4) | |||
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412 | (2) | |||
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414 | (2) | |||
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416 | (45) | |||
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416 | (2) | |||
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418 | (3) | |||
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421 | (3) | |||
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424 | (3) | |||
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427 | (3) | |||
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430 | (7) | |||
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437 | (7) | |||
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444 | (2) | |||
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446 | (7) | |||
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453 | (1) | |||
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454 | ||||
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443 | (2) | |||
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445 | (2) | |||
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447 | (14) | |||
Appendices | 461 | (30) | |||
Appendix A. Weapon-grade plutonium and highly enriched uranium production | 461 | (11) | |||
I. Weapon-grade plutonium production | 461 | (3) | |||
II. Highly enriched uranium | 464 | ||||
Table A.1. Representative conversion factors for reactors producing weapon-grade plutonium | 462 | (1) | |||
Table A.2. Conversion factors for gas-graphite reactor with natural uranium fuel | 463 | (1) | |||
Table A.3. Gas-graphite, air-cooled reactor with natural uranium fuel | 463 | (5) | |||
Table A.4. Overview of principal enrichment technologies | 468 | (1) | |||
Table A.5. Common examples of Enriched uranium output | 469 | (1) | |||
Table A.6. Weapon-grade uranium production (93% enriched) | 469 | (1) | |||
Table A.7. Current activites on uranium sepration and the level of such activities, by country | 470 | (1) | |||
Table A.8. Commercial enrichment plants | 471 | ||||
Figure A.1. The basic elements of a gaseous-diffusion plant | 465 | (1) | |||
Figure A.2. A gas centrifuge and a centrifuge rotor | 466 | (1) | |||
Figure A.3. EMIS configuration | 467 | (5) | |||
Appendix B. Calculation of plutonium production in power reactors | 472 | (7) | |||
Table B.1. Plutonium discharge rate by reactor type | 473 | (6) | |||
Appendix C. Sepration of plutonium from power-reactor fuel at reprocessing plants | 479 | (7) | |||
Table C.1. Plutonium separation from British Magnox power-rector fuel at B205 | 479 | (1) | |||
Table C.2. Plutonium separated from foreign Magnox fuel at B205 | 480 | (1) | |||
Table C.3. Plutonium separated from Magnox power-reactor fuel at UP1 (France) | 481 | (1) | |||
Table C.4. Plutonium separated from Magnox power-fuel at UP2 (France) | 482 | (1) | |||
Table C.5. Plutonium separated from oxide fuel at UP2 (France) | 483 | (1) | |||
Table C.6. Plutonium separated from oxide fuel at UP3 | 483 | (1) | |||
Table C.7. Plutonium separated from oxide fuel at WAK (Germany) | 484 | (1) | |||
Table C.8. Plutonium Separated from oxide fuel at Tokai-mura (Japan) | 484 | (1) | |||
Table C.9. World annual separation of civil plutonium, 1965-2000 | 485 | (1) | |||
Appendix D. Reaserch reactors(>1 MWth) using HEU fuel | 486 | (5) | |||
Table D.1. US operating reaserch and test reactors with power >1 MWth using HEU Fuel (as of mid-1995) | 486 | (1) | |||
Table D.2. US-supplied operating research and test reactors with power >1 MWth using HEU (.90%) fuel (as of mid-1995) | 487 | (1) | |||
Table D.3. Russian operating research and test reactors with power >1 MWth using HEU fuel (as of mid-1995) | 488 | (1) | |||
Table D.4. Russian-supplied operating research had test reactors with power >1 MWth using HEU fuel (as of mid-1995) | 488 | (1) | |||
Table D.5. Chinese and Chinese-supplied operating research and test reactors using HEU fuel (as of mid-1995) | 489 | (2) | |||
Index | 491 |
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