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c-10 Table C-6. Summary of Results for Cases Assuming High-Cost U308 Supply, 350 GWe Installed Capacity in Year 2000, and 15 GWe Installed Capacity Each Subsequent Year wtem Costa ($8) 1977 thm& 2050 dilcMted 8t 4.5% 7.5% 10.0% Lavelid !System R*rer bta (UllJIWlr) in m mi5 2025 2035 Oulative U 0 Cmsmptlm million tmh8thmgh 2025 2049 159 165 119 16.2 20.1 20.9 21.6 2.57 2.97 11 a a n-nsz & 579 I84 1029 651 1005 916 IO29 1029 1029 594 OU 1959 945 1205 I027 1959 1959 1947 c 362 440 507 47s 480 U9 110 509 u( 11 209 220 221 220 207 222 PI 229 119 129 1S2 135 133 128 IS2 1S2 1s 16.0 16.1 15.5 1t.2 16.2 15.7 15.7 15.7 16.0 19.6 17.7 16.1 20.0 18.0 l7.S 16.0 16.2 17.0 20.1 16.4 17.2 20.6 19.0 16.1 16.6 16.6 16.1 21.1 18.6 17.8 21.0 19.6 19.0 M.0 17.9 20.0 2.55 2.S 2.14 2.6S 2.50 2.W 2.18 2.14 2.29 2.96 2.95 2.75 2.S 2.W 2.94 2.62 2.6s 2.M Total U 0 Eolrmitted Btillim Tons) d&h 2025 2049 2.1 2.99 2.92 2.99 2.65 2.99 2.49 2.93 2.90 2.99 2.66 2.99 2.6.7 2.99 2.49 2.96 2.54 2.97 2-59 2.97 kina knual EnrWnent Pawin- 45 44 42 mt thwh 2050 (Milllm SiU/Yr) Ormilath Fnridnent (sillim 9u) th%25 204 9 inn) U ~ Utiliratim O ~ oms u~o,/~) 2025 2049 1.U 1.58 1.60 1.47 2.20 2.08 1.61 1.U 1.51 1.62 1.76 1.63 1.95 1.79 2.15 2.S 2.11 2.01 2.02 2.29 52% SMS S22t 2420 uo1 2867 SO86 242s 2469 25lS 52% 5042 SlP 1497 a65 2480 2908 1512 1114 1525 hri-t utiliutim (r~~ian srycw~)(~) in 2025 2.74 2.72 1.61 1.4s 2.0 2.07 1.75 1.49 1.46 1.76 2049 Loll 3.1 2.03 .92 2.70 2.12 2.06 1.03 1.O.l 1.17 llmlative Wlear W i t y hilt (-1 thrmgh 2025 2049 System Gnta (SB) 1977 thm@ 2050 divantcd at Levelired Spta hucr Costs pIills/Kvdir) in -WO 2015 2025 2035 Torn1 II 0 Committed Fcillion Tons) lh8qh 20% 2049 thrcugh 2025 2049 *System with standard LWR only. 591 94b bo7 1043 169 451 I8H 211 I20 129 1029 944 1029 1029 1029 1959 1071 142.3 I275 1959 502 495 490 470 500 219 226 221 213 218 131 116 133 129 IS1 18.1 16.0 15.4 16.0 15.9 15.5 15.4 19.7 17.1 15.9 19.5 17.2 16.6 15.9 20.4 17.6 16.6 20.1 18.1 17.4 15.9 21.0 17.9 17.0 20.5 19.0 18.2 14.4 2.54 2.27 2.96 2.92 2.92 2.81 2.99 2.99 42 . 40 (2Ilrn)(3) (2flll) 1.48 1.47 1.72 1.84 4939 2975 4931 2864 2.50 1.55 2.83 1.76 1.99 2.62 2.S5 2.14 1.93 2.70 2.98 2.% 2.91 2.69 2.43 2.89 2.81 2.77 2.36 2.92 2.99 2.199 2.98 2.91 34 6a bo s9 35 (2009) (2009) (2011) (2010) (2005) 1.32 1.70 2.19 2.54 1.94 2.54 1.45 2.02 1.33 1.86 2362 5066 nso 26117 2297 1492 2793 2091) 2340 1487 1.28 2.32 1.66 1.41 1.29 .87 2.P 1.79 1.59 .% 1029 1029 1959 1943 . 500 51s I18 222 IS1 IS2 15.4 15.6 15.9 16.S 15.9 17.0 14.4 17.6 1.93 2.07 2.69 2.83 2.% 2.58 2.91 2.97 35 YI (ZIIIIS) 12mw 1.35 1.42 1.66 1.97 2297 2506 1487 1528 1.29 l.P .95 1.01 c h3 . f‘ 1
-, ii I ; b i- ii L b 4 i L L i‘ -. W -latin klcar Capacity hilt (Ore) thmugh 2025 2049 System Costs ($I)) 1977 through 2050 discanted at 4.5% 7.5% 10.01 Levelired -tea bier Costs WIldMr) in 2000 2015 2025 2015 Total II 0 bitted (Uillion Tons) d&h 2025 2.90 2.81 2049 2.99 2.99 Cbxirn kvual Enrichcnt Rguire- mt thmugh 2050 (Million WJ/yr) (Lndstive Enrichr~~t millim SW) th?!25 2049 c-11 Table C-6 (cont.) 641 908 1029 lo03 1029 1029 1029 I029 1029 667 907 1959 1134 1747 1505 1959 1959 1959 Y7 494 524 551 566 549 529 52s us 192 222 225 214 2% a2 224 225 227 121 134 134 137 158 1% 134 113 I34 17.9 17.6 17.4 17.9 16.1 15.6 16.9 16.7 15.6 20.3 20.0 10.0 20.8 19.1 16.9 17.6 17.1 17.1 21.3 20.8 17.2 22.4 20.7 20.7 17.6 17.1 18.5 21.6 21.1 15.7 21.1 21.7 22.4 17.3 17.6 20.6 2.47 2.24 2.29 2.44 2.16 2.14 2.25 2.21 2.29 2.95 2.91 2.70 2.97 2.92 2.90 2.61 2.55 2.67 16 (ZOO$) (2001) u308 Utilization oms U~O~CW~) in’) 2025 4524 3095 2049 4489 son thriciment utilizatim willion SW/W)(~) in 2025 2049 Cutlstlw Hrlear Capacity hilt (Ore) thmigh 2025 2049 System Costs ($6) 1977 thmugh 2050 discomted at 1.10 1.24 1.45 1.35 2.02 1.17 2.18 1.37 2.63 2.90 2.70 2.79 2.55 2.50 2.69 2.72 ~ 2.99 2.98 2.90 2.63 2.57 2.98 4b 58 46 35 46 44 46 (2009) (2011) (2021) (2001) (2009) (2009) (2009) 1.61 1.90 1.61 1.2s 1.58 1.55 1.61 1.94 2.37 2.31 1.35 1.8.3 1.84 1.95 25% 2890 2620 2707 2482 2426 1391 2241 17W IS81 1345 1114 1520 1.57 1.90 1.58 1.19 1.54 1.51 1.57 .99 1.76 1.33 .W .% .91 1.00 568 1029 1029 803 958 917 1029 1029 1029 678 705 60s 1417 1959 155 io64 iool 19y1 1959 1791 703 xu 36.9 484 502 439 451 442 505 516 187 417 I68 217 219 209 210 209 221 220 224 197 201) 120 131 131 I29 I29 129 112 132 15O 124 IS2 Levelired Systea bier Costs (\(ills/Mr) in ZWO 16.2 16.0 15.7 17.7 15.9 15.6 15.6 15.6 15.3 17.4 17.6 2015 19.9 16.4 16.0 18.6 17.1 17.3 16.0 16.0 16.6 19.1 19.0 202s 20.5 16.6 15.6 16.9 17.7 16.1 16.1 16.1 16.8 19.7 19.6 2015 21.1 ,17.3 14.2 18.9 18.1 16.6 16.4 16.4 20.6 20.3 20.2 Total II 0 Caaitted (Uillim Tons) ti&h 2025 2049 2.55 2.19 1.97 2.35 2.n 2.31 2.15 2.12. 2.32 2.41 2.35 2.% 2.92 2.75 2.91 2.92 2.91 2.70 2.60 2.91 2.95 2.94 2.92 2.n 1.41 2.85 Z.M 2.63 2.42 2 3 2.77 2.89 2.67 2.99 2.98 2.95 2.99 2.99 2.99 2.93 2.93 2.90 2.99 2.99 Fhrinm krual Enrichcnt wire- 39 52 49 45 44 42 46 92 95 mt thmgh 2050 (Uillim WJ/yr) (20%’ (20& (ZOOS) (2011) (2017) (2011) (2009) (20091 (2009) (2011) (2011) Qrrulative Enrichmt (Billim SWI) thmgh 2025 1.59 1.71 1.49 1.60 1.69 1.62 1.53 1.50 1.64 2.69 3.25 2049 1.67 2.42 2.35 2.B 2.36 2.11 2.00 1.98 2.15 3.42 4.06 U ~ Utilization O ~ oms U~O~W) in(’) 2025 4973 2700 2502 3557 2920 ma2 us2 2316 2 ~ 2 4268 4078 2049 4%3 no5 1505 3497 2807 2914 1503 14% 1666 4258 4074 brictncnt ~ti~~zation willim SU/W)(~) in 2025 2.70 1.66 1.45 2.24 1.76 1.77 1.48 1.45 1.60 3.97 4.60 2049 3.10 1.71 1.15 2.75 2.22 2.10 1.02 1.01 1.20 4.86 5.53 (1) Cumulative U,Os consumed through year 2050 (including forward comnitments) per cumulative nuclear capacity built through 2050. (2) Cumulative enrichment requirements through 2050 per cumulative nuclear capacity built through 2050. (3) Year in which maximum enrichment requirements occur.
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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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‘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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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
Page 273 and 274: 13 A-13 L" efficient of the units d
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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
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
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Page 297: E , 1 ' b _. I ' L 1 b _- i G i' b
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 and 314: L L i il L t W 0-9 Table D-4. Summa
Page 315 and 316: -- Lid c i' .- .b) i Internal Distr
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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