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D-10 Table D-5. Variation of U308 Price with Time for Various Nuclear Cases U308 Price ($/lb) - Year - 1L - 2L - 3L - 4L - 5L - 6L - 7L - 8L 1987 76 81 83 73 82 83 83 82 1997 104 112 114 99 113 114 114 113 2007 136 150 153 130 150 153 153 151 2017 157 177 175 151 177 175 175 175 2027 167 185 179 158 184 180 180 180 2037 172 189 180 158 186 180 180 180 2047 173 195 180 158 189 180 180 180 L f c c
-- Lid c i' .- .b) i Internal Distribution 0 RNL - 5 388 Di s t . Category UC-80 1. L. S. Abbott 38. H. R. Meyer 2. R. G. Alsmiller 39. J. D. McGaugh 3. T. D. Anderson 40. F. R. Mynatt 4. W. B. Arthur, ORGDP 41. K. J. Nott 5. S. Baron 42. A. R. Olsen 6. D. E. Bartine 43. R. W. Peelle 7. H. I. Bowers 44. H. Postma 8. J. T. Bradbury, ORGDP 45. R. T. Prim 9. R. E. Brooksbank 46. B. E. Prince 10. W. D. Burch 47. R. H. Rainey 11. T. J. Burns 48. J. P. Renier 12. W. L. Carter 49. P. S. Rohwer 13. J. C. Cleveland 50. T. H. Row 14. T. E. Cole 51. R. T. Santoro 15. A. G. Croff 52. D. L. Selby 16. J. G. Delene 53. R. L. Simard 17. J. R. Engel 54. G. R. Smolen 18. D. E. Ferguson 55-75. I. Spiewak 19. G. F. Flanagan 76. W. G. Stockdale 20. M. H. Fontana 77. J. E. Till 21. E. H. Gift 78. D. B. Trauger 22. P. M. Greebler (Consultant) 79. H. E. Trammel1 23. P. M. Haas 80. R. E. Uhrig (Consultant) 24. W. 0. Harms 81. J. E. Vath 25. J. F. Harvey 82. B. L. Vondra 26. R. F. Hibbs 83. D. R. Vondy 27. D. T. Ingersoll 84. C. R. Weisbin 28. 3. D. Jenkins 85. 3. R. White 29. D. R. Johnson 86, R. Wilson (Consultant) 30. P. R. Kasten 87. R. G. Wymer 31. H. E. Knee 88. A. Zucker 32. M. Levenson 89-90. Central Research Library 33. W. B. Loewenstein (Consultant) 91. Document Ref. Section 34. A. L. Lotts 92-131. EPD Reports Office 35. R. S. towrie 132-133. Laboratory Records Dept. 36. F. C. Maienschein 134. Laboratory Records , RC 37. B. F. Maskewitz External Distribution DOE, Washington, D.C. 20545 135. W. W. Ballard, Asst. Director, Fuel Cycle Development 136. E. S. Beckjord, INFCE Coordinator 137. Harold Bengelsdorf, Office of Nuclear Affairs 138. S. T. Brewer, Director, Program Planning and Analysis 139. Phillip Clark, Assoc. Director for Reactors, Div. of Naval Re act or s
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Interim Assessment of the Denatured
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i L i b I, i L L bi L L Contract No
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1, L L t i Ltr 1 L L V PREFACE AND
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L i Li 1, I b k b id ii t L id b i
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I L bi i; L 7.3.1. Possible Procedu
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i xi I b L ABSTRACT A fuel cycle th
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I b .- i, hd t t CHAPTER 1 INTRODUC
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L .- k id .- I L: _ - I iclr .- i b
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huJ -- AI I ' b --- I bl --- t L L
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-- t Li - I' b -. c (u I i ai L i i
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L - i' u i Lt L r- L t- b L 2-7 den
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2-9 1. Nuclear power is limited to
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e Isr i L i- b t CHAPTER 3 ISOTOPIC
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232" Fig. 3.0-1. Decay of 232U. ORN
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3-6 3.1. ESTIMATED U CONCENTRATIONS
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3-8 The values in Table 3.1-2 are a
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3-1 0 3.2. RADIOLOGICAL HAZARDS OF
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3-1 2 232u IN RECYCLED HTGR FUEL (p
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3-14 3.2.2 Toxicity of 232Th Given
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1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11.
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3.18 There are three approaches whi
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1 i i 3-20 3.3.2. Fabrication and H
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The 3-22 3.3.3 Detection and Assay
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3-24 3.3.4. Potential Circumvention
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3-26 - either large centrifuge pilo
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! 3-28 Table 3.3-3. Enriched Proauc
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3-30 The high alpha activity of ura
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3- 32 Table 3.3-7. Sumry of Results
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3-34 statistical redundancy through
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introduce time, cost and visibility
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3-38 An additional factor relative
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I b t I t L 1; L t ki 4.0. 4.1. CHA
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L L _ _ { i J _- \ I b B u il c _.
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Y m I I I . aro ID0 10.00 4-5 ORNL-
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t .. -. F 4d -- I ' L 0- 122, L _-
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L L; L t -I I ' b L -- t i b -- I;
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_- I -- L i d .-- L 4-1 1 Reference
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_- id L t I , 4d i, L id L 5 bi t h
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-- - . & I I ' h I ' Y 61 L -- I( L
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u -- x i I*i 1- bi 4-1 7 The use of
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la - i , I br -_ t c c L e L 4-1 9
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4-21 Case B" is a modification of C
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c 4-23 L i a L L 4.2. SPECTRAL-SHIF
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4-25 Initial analyses of spectral-s
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h 1' b t c i--; & I- & 1: i f 4-27
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c- i L L e I b 4-29 . safeguards fo
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L t i- bi L L t i 4-31 a significan
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~ kc'l c" -1 r-"! r! r-'i c Table 4
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F-- I iJ L ii - L c c 4-35 Referenc
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c r- L i] L h L __ f; t 4-37 trons
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Table 4.4-1. Fuel Utilization Chara
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L I 1 I Ld I ie i-- 1 t' 4-41 4.4.2
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4-43 Table 4.4-4. PBR Coated Partic
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HEU/Th 0.59 Seed i3 Breed 0.58 HEU/
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L i; 1 I i; i 1. 2. 3. 4. 5. 6. 7.
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4-49 Table 4.5-1. Fuel Utilization
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ments. 4-51 The calculations for LM
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1. 2. 3. 4. 5. 6. 7. 8. 4-53 0 77-1
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Table 4.6-1. Comparison of Fuel Uti
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4-57 _I 10 10' 2 2' CASE NUMBER -.
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4-59 Most of the information availa
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- i b k L L -- I , b -- I .- I Li L
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4-63 on only the preliminary data p
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c e E c
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! 5-4 5.1. REACTOR RESEARCH AND DEV
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5-6 As has been pointed out above,
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5-8 the LMFBR on its reference cycl
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5-10 The fuel performance program u
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. 5.1.2. Government Research and De
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5-1 4 The first aspect of large pla
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5-1 6 and should also address metho
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I DATA BASE DEMu)pMENT DEMO DESIGN
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j ~ 5-20 The R,D&D costs are highes
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5-22 In the case of metal-clad oxid
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5-24 5.2.2. Research, Development,
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5-26 program, including hot testing
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c c
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6-4 persed areas ensured - a fact w
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6-6 6.1.2. Reactor Options The reac
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Reactor/Cycl ea LWR-U5(LE)/U-S LUR-
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6-10 6.1.3. Nuclear Policy Options,
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Table 6.1-4. Nuclear Policy Options
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SWU SWU 6-14 UZJS USILEINS WYI U5IL
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6-16 n nM MEDL nows.1 Option 4: In
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6-18 HM HEDL7OOl.70.3 Option 6: In
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SRCIFIED CONSTRUCTION LlMllLD INTRO
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50- 40 6-22 c Y \ VL - :-: F 30- -
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6-24 The potential nuclear contribu
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%- f $400 J 2 s 2, 1 THE LWR FOLLOW
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141.6 ST - U308 4 7.2 lo3 swu ENRIC
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6-30 reactor. Since this increase i
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‘9. ,1 ST ‘3O8 6-32 12 Kg HM I
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6-34 1HE LWR WITH FISSILE UUNIUM PC
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THE LWR WITH PURONIUM MlNUllUTlON A
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6-38 be located in energy centers a
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6-40 installed capacity must be han
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lm, 1 I I I I mf RR WITH UGHT rwrmi
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6-44 6.2.7. Converter-Breeder Syste
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25.2 ST swu 6-46 19 Kg fir Pu 13 Kg
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6-48 Table 6.3-2. Summary of Result
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6-50 (4) If all plutonium produced
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I d r-- 1 > w I r- k z r L id r- .
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L 1 L u without benefit of U.S. exp
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L a, - L i -- k; L t IJ L 7-7 While
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7-9 Viewed solely from the plutoniu
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L L i; i; 7-1 1 routinely in LWRs a
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'I 7-1 3 t I: k: The isotopic compo
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U L L L L ld 1 i" * required 233U m
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I I, i 7-1 7 ii I 1 I L L k L i Thr
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li i i L Li L & I ' i kr ii L i h i
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7-21 7.3. PROSPECTS FOR IMPLEMENTAT
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L I L t L i L i 1 L 7-23 7.3.1. Pos
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7-25 7.3.2. Considerations in Comme
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.. I b k; L; i b b 1J I L 7-27 cycl
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7-29 7.4. ADEQUACY OF NUCLEAR POWER
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L i' hd .- - I ' i t L i' b i -' b
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x ibd 1 .. I i, L -- i t Table 7.4-
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7-35 cycled in Pu/Th converters, th
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L 1' b I_- ,- i b -- I ' b L 7-37 T
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..a 4 I- 1 ' u c1 Y u L 7-39 betwee
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L e, I I ' lb t 7-41 Systems that u
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e-. . ! hr L3 z i- b: i- b L c i li
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7-45 j I Table 7.5-1. Integrated As
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- isi. c ‘Id i L c 7-47 Although
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e Other e e e On the e 7-49 technol
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t a APPENDICES
Page 263 and 264: A-3 Appendix A. ISOTOPE SEPARATION
Page 265 and 266: I] 1- $i ill 8 LI b' The Gas Centri
Page 267 and 268: id A- 7 The Component Preparation L
Page 269 and 270: i ?L 1- U t L fl bi L c u La -- ti
Page 271 and 272: p; ‘U i-- L ,c c Japan A-1 1 Tabl
Page 273 and 274: 13 A-13 L" efficient of the units d
Page 275 and 276: L L L t I h h u L; _- t f is throug
Page 277 and 278: u A-1 Aerodynamic Methods 7 Both th
Page 279 and 280: i i d .- I . ii hi L i: i t ' Li 1
Page 281 and 282: la t L I I, lj ir 1 Li c I L L' B-1
Page 283 and 284: i; 1 t u 1 1 B-3 Table 8.5. Reactor
Page 285 and 286: Table 6-7. Marginal Costs of U308 a
Page 287 and 288: LJ L L1 a .E 4' P Y W 5 18 2 16 : 0
Page 289 and 290: Appendix C. DETAILED RESULTS FROM E
Page 291 and 292: 1 i; Li b L lkd t L L I hd I ' L; i
Page 293 and 294: L c-5 The introduction of the class
Page 295 and 296: i ' ibd 1 b i L L i L I Li . . b b
Page 297 and 298: E , 1 ' b _. I ' L 1 b _- i G i' b
Page 299 and 300: -, ii I ; b i- ii L b 4 i L L i‘
Page 301 and 302: _- I ii I _ _ I L I td C i b L i, L
Page 303 and 304: Qulatiw klur W i t y hilt (*I thrmg
Page 305 and 306: L c c b - i ii L r D-1 Appendix D.
Page 307 and 308: L L L L [i i” Table D -2. Maximum
Page 309 and 310: Fig. D-2 (cont.) 25W I I I I I (I)
Page 311 and 312: [i energy center. It can be seen fr
Page 313: L L i il L t W 0-9 Table D-4. Summa
Page 317 and 318: It e L L L t u I' f ' ki Federal Ag
Page 319: u 1' 1" Outside Organizations (cont
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