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141.6 ST - U308 4 7.2 lo3 swu ENRICH. 80.1 lo3 swu 6-28 235- U5CE)b-J 2,907 Kg HM 51 Kg U 0.08 GWe 1,761 Kg HM CF = 60.3 THROWAWAY [17,mo 543 Kg U2% 0.92 GWe CF = 60.3 28,730 Kg HM ) Case 1L: LWRs Only; High-Cost U308 Supply. 23.1 lo3 SWU 53.7 lo3 swu 165 Kg U235 5,650 Kg HM 410 Kg U235 15,870 Kg H 0.26 GWe CF = 60.3 THROWAWAY U5(LE)/U 23.750 Kg HM 0.74 GWe CF = 60.3 (b) Case 1s: LWRs Followed by SSCRs; High-Cost U308 Supply. I HEDL 7805-090.34b I HEDL 7805-090.34a Fig. 6.2-12. Utilization and Movement of Fissile Material in Nuclear Systems Consisting of Converters Operating on Throwaway/Stowaway Cycle (year 2035). (Note: Except for Case lL, which utilizes <strong>the</strong> extended exposure LWR, all LWRs included here and in subsequent systems are standard LWRs.) . . L u L I L i; L I! L I; L F 'I .Li c
d t Y L Fig. 6.2-12 (cont.) -133.3 ST U 0 3 8 4 40.9 X;$ SWU ENRICH. 51.2 X-l$ SWU 6-29 291 Kg urn ,9,967 Kg HM 260 Kg Urn -3,495 Kg HM CF40.3 5,146 Kg HM - (c) Case 1G: HEDL 7805-090.31 LWRs Followed by HTGRs; High-Cost U308 Supply. \ 18.6 x Id SWU 13.9 J THROWAWAY HEDL 78Md90.58 (d) Case 1H: LWRs Followed by HWRs; High-Cost U308 Supply.
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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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- - I 4d _- t .- ! Lili L Ld id .-
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L .- k id .- I L: _ - I iclr .- i b
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I, G - -- I id ..- ! I _. I: L _.-
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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
Page 138 and 139: ! 5-4 5.1. REACTOR RESEARCH AND DEV
Page 140 and 141: 5-6 As has been pointed out above,
Page 142 and 143: 5-8 the LMFBR on its reference cycl
Page 144 and 145: 5-10 The fuel performance program u
Page 146 and 147: . 5.1.2. Government Research and De
Page 148 and 149: 5-1 4 The first aspect of large pla
Page 150 and 151: 5-1 6 and should also address metho
Page 152 and 153: I DATA BASE DEMu)pMENT DEMO DESIGN
Page 154 and 155: j ~ 5-20 The R,D&D costs are highes
Page 156 and 157: 5-22 In the case of metal-clad oxid
Page 158 and 159: 5-24 5.2.2. Research, Development,
Page 160 and 161: 5-26 program, including hot testing
Page 162 and 163: c c
Page 164 and 165: 6-4 persed areas ensured - a fact w
Page 166 and 167: 6-6 6.1.2. Reactor Options The reac
Page 168 and 169: Reactor/Cycl ea LWR-U5(LE)/U-S LUR-
Page 170 and 171: 6-10 6.1.3. Nuclear Policy Options,
Page 172 and 173: Table 6.1-4. Nuclear Policy Options
Page 174 and 175: SWU SWU 6-14 UZJS USILEINS WYI U5IL
Page 176 and 177: 6-16 n nM MEDL nows.1 Option 4: In
Page 178 and 179: 6-18 HM HEDL7OOl.70.3 Option 6: In
Page 180 and 181: SRCIFIED CONSTRUCTION LlMllLD INTRO
Page 182 and 183: 50- 40 6-22 c Y \ VL - :-: F 30- -
Page 184 and 185: 6-24 The potential nuclear contribu
Page 186 and 187: %- f $400 J 2 s 2, 1 THE LWR FOLLOW
Page 190 and 191: 6-30 reactor. Since this increase i
Page 192 and 193: ‘9. ,1 ST ‘3O8 6-32 12 Kg HM I
Page 194 and 195: 6-34 1HE LWR WITH FISSILE UUNIUM PC
Page 196 and 197: THE LWR WITH PURONIUM MlNUllUTlON A
Page 198 and 199: 6-38 be located in energy centers a
Page 200 and 201: 6-40 installed capacity must be han
Page 202 and 203: lm, 1 I I I I mf RR WITH UGHT rwrmi
Page 204 and 205: 6-44 6.2.7. Converter-Breeder Syste
Page 206 and 207: 25.2 ST swu 6-46 19 Kg fir Pu 13 Kg
Page 208 and 209: 6-48 Table 6.3-2. Summary of Result
Page 210 and 211: 6-50 (4) If all plutonium produced
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Page 215 and 216: L 1 L u without benefit of U.S. exp
Page 217 and 218: L a, - L i -- k; L t IJ L 7-7 While
Page 219 and 220: 7-9 Viewed solely from the plutoniu
Page 221 and 222: L L i; i; 7-1 1 routinely in LWRs a
Page 223 and 224: 'I 7-1 3 t I: k: The isotopic compo
Page 225 and 226: U L L L L ld 1 i" * required 233U m
Page 227 and 228: I I, i 7-1 7 ii I 1 I L L k L i Thr
Page 229 and 230: li i i L Li L & I ' i kr ii L i h i
Page 231 and 232: 7-21 7.3. PROSPECTS FOR IMPLEMENTAT
Page 233 and 234: L I L t L i L i 1 L 7-23 7.3.1. Pos
Page 235 and 236: 7-25 7.3.2. Considerations in Comme
Page 237 and 238: .. 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
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A-3 Appendix A. ISOTOPE SEPARATION
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I] 1- $i ill 8 LI b' The Gas Centri
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id A- 7 The Component Preparation L
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i ?L 1- U t L fl bi L c u La -- ti
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p; ‘U i-- L ,c c Japan A-1 1 Tabl
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13 A-13 L" efficient of the units d
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L L L t I h h u L; _- t f is throug
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u A-1 Aerodynamic Methods 7 Both th
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i i d .- I . ii hi L i: i t ' Li 1
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la t L I I, lj ir 1 Li c I L L' B-1
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i; 1 t u 1 1 B-3 Table 8.5. Reactor
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Table 6-7. Marginal Costs of U308 a
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LJ L L1 a .E 4' P Y W 5 18 2 16 : 0
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Appendix C. DETAILED RESULTS FROM E
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1 i; Li b L lkd t L L I hd I ' L; i
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L c-5 The introduction of the class
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i ' ibd 1 b i L L i L I Li . . b b
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E , 1 ' b _. I ' L 1 b _- i G i' b
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-, ii I ; b i- ii L b 4 i L L i‘
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_- I ii I _ _ I L I td C i b L i, L
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Qulatiw klur W i t y hilt (*I thrmg
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L c c b - i ii L r D-1 Appendix D.
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L L L L [i i” Table D -2. Maximum
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Fig. D-2 (cont.) 25W I I I I I (I)
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[i energy center. It can be seen fr
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L L i il L t W 0-9 Table D-4. Summa
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-- Lid c i' .- .b) i Internal Distr
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It e L L L t u I' f ' ki Federal Ag
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u 1' 1" Outside Organizations (cont
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