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7-32 Table 7.4-1. Description of Fuel Cycle Options* Throwaway/Stowaway Option (see Fig. 6.1-1): Option 1. LEU converters on once-through cycle. Plutonium-Uranium Options (see Fig. 6.1-2): Option 2. Pu/U recycle option; LEU converters outside center; Pu/U converters inside center; HTGRs inside center operate on 235U/Th, 233U/Th, and Pu/Th. Option 3. Pu/U recycle option; LEU converters outside center; Pu/U converters and breeders inside center; HTGRs inside center operate on 235U/Th, 233U/Th, and Pu/U. Denatured Uranium Options Using Converters Only (see Fig. 6.1-3): Option 4. Option 5U. Plutonium throwaway option; LEU and denatured 235U and 233U converters outside center; no reactors inside center; U only recycled. Plutonium minimization option; LEU and denatured 235U and 233U converters outside center; Pu/Th converters inside center; U and Pu recycl ed. Option 5T. Same as 5U without denatured 235U converters. Denatured Uranium Options Using Both Converters and Breeders (see Fig. 6.1-4): Option 6. Light transmutation option; LEU and denatured 235U and 233U converters outside center; Pu/Th converters and Pu-U/Th breeders inside center. Option 7. Option 8. Light transmutation option with denatured breeder; LEU converters, denatured 23sU converters, and denatured 233U converters and breeders outside center; Pu/Th converters and Pu-U/Th breeders inside center. Heavy transmutation option; same as Option 7 except inside breeder is a Pu-Th/Th breeder. *Four cases considered under each option, identified by letters L, S, H, and G to denote type of converter employed in addition to LEU-LWRs (L = LWR, S = SSCR, H = HWR, G = HTGR). The effect of varying the fuel cycle system can be seen by reading across Table 7.4-2 and the effect of changing the converter reactor option can be deduced by 'reading down a column. An installed nuclear canacity of 1100 GWe in year 2050 indicates that the projected energy demand is fully met by tne reactors in a given nuclear fuel cycle system. c L I: L 6: L I: c
x ibd 1 .. I i, L -- i t Table 7.4-2. (Note: 7-33 Maximum Nuclear Capacity of Various Nuclear Power Options and Year in Which Maximum Occurs A capacity of 1100 GWe in year 2049 meets demand.) Maximum Instal led Nuclear Capacity (GWe)/Year rnmimwn occurs Converter Reactor Opt i on 1 2 3 4 5u 5T 6 7 8 HTGRs (GI 433 2009 440 2009 444 2021 437 2009 729 2027 763 2029 852 2035 783 2031 Non-FBR Systems, Options 1, 2, 4, and 5 With High-Cost U308 Supply 61 1 1100 585 71 6 637 2022 2049 2029 2027 2022 661 1100 660 820 764 2023 2049 2023 2053 2029 630 1100 756 91 5 856 2022 PO49 2031 2041 2035 818 1100 545 671 638 2033 2049 2019 2023 2021 With Intermediate-Cost U308 Supply 968 1100 1002 1062 1012 2041 2049 2047 2049 2047 1078 1100 1084 1100 1100 2049 2049 2049 2049 2049 1062 1100 1084 1100 1100 2049 2049 2049 2049 2049 1100 1100 971 1065 996 2049 2049 2041 2049 2045 1100 2049 1100 2049 1100 2049 1091 2049 1100 2049 1100 2049 1100 2049 1100 2049 1100 For the high-cost U308 supply case (3 million ST U308 below $160/lb), it is evident that introducing advanced converters on the throwawayfstowaway fuel cycle (Option 1 ) has little effect on the maximum attainable nuclear capacity. This is directly due to the introduction dates assumed for the advanced converter reactors. By the time the converters 2049 1100 2049 1100 2049 1100 2049 1100 2049 1100 2049 1100 2049 1100 2049 1087 2049 1084 2049 1100 2049 958 2041 1097 2049 1100 2049 1100 2049 1100 2049 '
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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
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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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Page 194 and 195: 6-34 1HE LWR WITH FISSILE UUNIUM PC
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Page 198 and 199: 6-38 be located in energy centers a
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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 239 and 240: 7-29 7.4. ADEQUACY OF NUCLEAR POWER
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Page 259 and 260: e Other e e e On the e 7-49 technol
Page 261 and 262: 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
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Page 277 and 278: u A-1 Aerodynamic Methods 7 Both th
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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
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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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