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. . . . . . . -..-. - . . . Table 4.4-7. Fuel Utilization Characteristics for Equilibrium Cycles of PBRs Under Various Fuel Optionsa with No Recycle --- .. I . . . . ~ ~ .... Fuel Conversion Fuel Loading Discharge Isotopic Fraction Burnup Case Type Ratio Elementsb (kg/GWe-yr) (kg/GWe-yr 1 of Oi scharge Pu (HWO/kg HM) Dispersible Resource-Based Fuels 1 LEU 0.58 L1 + L2 575 23511 2 MEU/Th 0.58 M2 3 Seed & Breed 0.56 MEU/Th 52 82 6168 23eU 6743 Utot. 4158 Th - 534 23511 2163 238U 2697 Utot* 540 235U 2190 238U 2730 Utot* 4 70 Th 93 23511 80 236U 5719 238U 5892 Utot. 42 239(P~,Np) 26 240Pu 21 24'Pu 24 242Pu 113 Putot' 3881 Th 91 233(U,pa) 22 23411 39 23511 79 2360 1965 238U 2195 Utot. 9 239(Pu,Np) 9 2'0Pu 5 24'Pu 13 242Pu 36 Putot* 30 235U 81 236U 1982 2eaU 2093 Utot' 3881 Th 82 233(U,Pa) 22 23411 4 235u 1 23611 108 Utot' 0.37 2391P~.No) ~ .. 0.23 240Pu 0.19 241Pu 0.21 242Pu 0.25 239(P~,Np) 0.26 240Pu 0.14 0.34 '"Pu 242Pu Puf/Putot' = 0.39 0.24 239(Pu,Np) 0.25 240Pu 0.14 241Pu 0.38 242Pu Puf/Putot' = 0.38 100 100 201 35 "_I ~. P P .
HEU/Th 0.59 Seed i3 Breed 0.58 HEU/Th M1 s1 B1 Reference Fuels 6302 Th - - 495 235u 38 23% 533 utot* 1287 Th - 496 235u ;8 23% 534 4983 Th 5794 Th 128 233(U,Pa) 38 234U 23 235U 73 236u 30 238U 292 Utot* 1.166 Putot* 1185 Th 155 Utot. 0.227 239(Pu.Np) 0.257 240Pu 0.120 241Pu 0.500 2'2Pu 1.106 Putot' 4594 Th :Calculated for 1000-We plant operating at 75% capacity. See Tables 4.4-3 through 4.4-6 for descriptions of cases and fuel elements. =Reference fuels are considered only as limiting cases. 91 233(U,Pa) 29 234U 5 23511 1 23% 126 Utot' 0.23 23g(Pu,Np) 0.21 24OPu 0.13 Z41Pu 0.44 242PU Puf/Putoto = 0.36 243 0.21 239(PuBNp) 0.23 24oPu 0.11 2"Pu 0.45 242Pu Puf/Putot* = 0.32 100 48 f P VI
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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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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
Page 64 and 65: 3-34 statistical redundancy through
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Page 68 and 69: 3-38 An additional factor relative
Page 71 and 72: I b t I t L 1; L t ki 4.0. 4.1. CHA
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Page 75 and 76: Y m I I I . aro ID0 10.00 4-5 ORNL-
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Page 81 and 82: _- I -- L i d .-- L 4-1 1 Reference
Page 83 and 84: _- id L t I , 4d i, L id L 5 bi t h
Page 85 and 86: -- - . & I I ' h I ' Y 61 L -- I( L
Page 87 and 88: u -- x i I*i 1- bi 4-1 7 The use of
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Page 91 and 92: 4-21 Case B" is a modification of C
Page 93 and 94: c 4-23 L i a L L 4.2. SPECTRAL-SHIF
Page 95 and 96: 4-25 Initial analyses of spectral-s
Page 97 and 98: h 1' b t c i--; & I- & 1: i f 4-27
Page 99 and 100: c- i L L e I b 4-29 . safeguards fo
Page 101 and 102: L t i- bi L L t i 4-31 a significan
Page 103 and 104: ~ kc'l c" -1 r-"! r! r-'i c Table 4
Page 105 and 106: F-- I iJ L ii - L c c 4-35 Referenc
Page 107 and 108: c r- L i] L h L __ f; t 4-37 trons
Page 109 and 110: Table 4.4-1. Fuel Utilization Chara
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Page 113: 4-43 Table 4.4-4. PBR Coated Partic
Page 117 and 118: L i; 1 I i; i 1. 2. 3. 4. 5. 6. 7.
Page 119 and 120: 4-49 Table 4.5-1. Fuel Utilization
Page 121 and 122: ments. 4-51 The calculations for LM
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Page 125 and 126: Table 4.6-1. Comparison of Fuel Uti
Page 127 and 128: 4-57 _I 10 10' 2 2' CASE NUMBER -.
Page 129 and 130: 4-59 Most of the information availa
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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
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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
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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
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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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