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D-8 Table D-3. Summary of Results for Cases Assuming High-Cost U308 Supply, an Electrical <strong>Energy</strong> Growth Projection, and Power Systems Including Both Nuclear and Coal Power Plants Cmulative Capacity Built (me) through 2050 liuclear FaSSil *tern Costs (SB) 1977 thmugh 2050 Discomted B 4 1/21 7 1/21 101 Annual coal connmpcim in 2025 (10' tans) 2050 Total c"$"ittd U308 through 2050 (10 tosls) --- lL 2L 3L 4L - 705 4611 2663 2653 1804 1733 1701 787 764 758 479 470 468 5.22 3.72 3.15 2.92 3.50 3.56 3.42 4.75 4.60 3.55 4.92 5.06 933 4383 1806 791 483 -- 5L 6L - n 81 - 1684 2597 3632 2719 1724 1703 761 760 468 469 4.79 3.59 2.91 2.88 3.13 3.18 3.62 3.68 4.75 4.33 4.85 4.37 2.02 1.20 2595 2721 1703 760 469 2.91 3.68 4.33 4.37 1909 3407 in8 761 469 ' 54 65 73 72 75 80 80 79 (ZOOS) (3) (20ll) (2009) (ZOOS) (2015) (2011) (20W (rn15) 2.12 3.11 2.89 2.53 3.40 3.11 3.11 3.37 t] 5.04 3.10 1.90 3.41 2.88 1.68 1.68 2.50 3.01 1.96 1.09 Installed Capacity (GWe) in Year 2026/Levelited Power Costs (Mill/Kwhr) in Year 2025 2.71 1.20 - n Reactor - 1L - 2L - 3L - 4L - SL - 6L - 8L LWR-U5(LE)/U US{LE)/u-EE us m1/um u3 (DE)/U/Th wu pu/Th 36/23.2 225/22.3 579/21.1 336/22.3 513/20.8 - 196/19.5 113/21.6 189/22.5 157/20.0 - 661/21.2 0/23.5 120/20.6 181/20.1 594/20.7 0/23.2 190/19.6 52/22.1 594/20.7 0/23.2 190/19.6 52/22.1 668/20.8 0/23.1 230/20.8 102/23.0 FBR-PU-U/u - 444/18.4 - PU-Um Pu-mm u3-um - 408/19.4 40W19.4 3.25 3.69 4.70 4.77 1.77 - 104/22.6 - 0/23.0 0/25.0 Fossil 1934 1280 1042 1736 1233 951 951 1091 Total Nuclear 261 915 llS3 459 962 1244 1244 1104 (1) Cumulative U308 comsumed through 2050 (including forward comnitments) per cumulative nuclear capacity built through 2050. (2) Cumulative enrichment requirements through 2050 per cumulative nuclear capacity built through 2050. (3) Year in which maximum enrichment requirements occur. L E L c
L L i il L t W 0-9 Table D-4. Summary o f Results for Cases Assuming Intermediate-Cost U308 Supply, an Electrical <strong>Energy</strong> Growth Projection, and Power Systems Including . Both Nuclear and Coal Power Plants Cunulative Capacity Built (ab) through 2050 Nuclear Fossil -------- 1LU 2LU 5LU 4LU 5LU 6LU 7LU 8LU 1257 4059 2523 2793 3415 1901 1815 3501 2701 2615 3296 2020 3338 1978 2727 2589 System Costs [$Bl 1977 through 2050 Discounted e 4 1/2\ 7 1/28 101 1732 759 466 1652 738 459 1622 734 458 1743 770 474 1643 755 458 1624 735 459 1624 735 459 1638 736 458 Annual Coal Consunption in 2025 (lo9 tons) ative U 0 Consunption 3kns) tiLough 4.13 2.28 1.92 3.41 2.22 1.82 1.77 2.01 2026 2050 Total Cngnitted U308 throu& 4.75 6.10 4.60 7.44 4.43 6.29 4.41 5.75 4.63 7.40 4.48 5.75 4.50 5.75 4.60 6.62 2050 (10 tons) 6.28 7.88 6.90 5.94 7.99 5.87 5.89 6.84 Maximm Annual Enrichment zFwem$ throu& 2050 93 (2013) 103 (2025) 93 (2011) 119 (2011) 111 (2023) 101 (2011) 102 (2011) 103 (2017) Cunulati e Enridment through 2050 (106 sku) 3.80 4.87 3.96 4.78 5.26 4.12 4.12 4.73 u308 utilization(') Enr'chment 5.00 3.12 2.02 3.27 2.96 1.78 1.76 2.51 (10' sI\u/ae) 3.02 1.93 1.16 2.63 1.95 1.25 1.23 1.73 Installed Capacity (GWe) in Year 2026/Levelized Power Costs (Mills/Kwhr) in Year 2050 Reactor 1LU - 2LU - 3LU - 4LU, - 5LU - 6LU - 8LU - - LwR-US(LE)/U 61/22.4 1028/19.8 827/19.4 235/20.6 1108/19.9 874/19.2 872/19.2 1028/19.7 US(LE)/U-EE 675/21.6 u5 W)/U/Th 489/21.6 0/21.9 0/21.3 0/21.3 0/21.7 U3(E)/U/Th 336/20.4 143/19.5 219/19.6 221/19.6 280/19.7 pu/v 441/19.2 269/18.7 - PUm - 235/18.9 63/20.8 56/20.8 119/21.3 FBR-h-U/U - 516/17.3 - PU-U/Th - 486/19.2 509/19.2 - Pu-Th/Th- - 136/20.6 us-urn 0/23.7 0/23.5 Fossil 1458 725 583 1135 7lO 553 537 632 Total Nuclear 736 1470 1612 1060 1485 1642 1658 1563 (1) Cumulative U3O8 consumed through 2050 (including forward comi tments) per cumulative nuclear capacity bui 1 t 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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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
Page 261 and 262: t a APPENDICES
Page 263 and 264: A-3 Appendix A. ISOTOPE SEPARATION
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Page 267 and 268: id A- 7 The Component Preparation L
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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 and 298: E , 1 ' b _. I ' L 1 b _- i G i' b
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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: [i energy center. It can be seen fr
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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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