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FBR-h-u/IJ FBR-FU-U/lh FBR-FU-RJlh FBR-u3-u/Th FBR-h-U/IJ FBR-FU-U/Th FBR-Pu-Th/Th m-u3-u/Th , *System with standard LUR only. C-16 Table C-8 (cont.) Installed Carurcitv GWeVLevelized Fwer Cost Mills/Kwhrl in year 202s - 3L - 41 - SUL 460/1S.8 57/18.8 S41A6.9 3/17.8 7V17.0 122/16.2 sn - - 6L - 7L 703/20.6 30/20.S S23/17.0 S44/16.3 SSl/lS.8 SSl/lS .8 - 69S/l9.8 - - 439/19.0 0/16.3 0/16.3 -. - 243/17,8 72/16.4 72/13.2 72/13.2 216h6.8 254/14.9 - 122DS.8 103112.5 103D2.S - - 1s 109/20.3 2s 8V16.4 2m2.s - - 3s llS/lS.4 239/1S.7 279/14.4 - 4s S7/17.9 380/17.6 - 5us 184hS.6 0/17.3 630/19.5 418D6.0 346/1S.O 0/17.8 302h7.1 500/1S.S 128/1s. s 128/1S.S - 1H - w 232D9.S 480/17.8 0/22.9 0123.9 507/20.4 0/20.6 - 259/19.6 1C - - x 0/14.1 ft - - 4H 359D6.1 666h9.5 0/22.2 0/2S.4 0/19.3 0/21.8 63/21.7 10/20.4 0/18.8 - 380/14.6 - - m 184/15.6 300/1S.S 128/15.S 128/lS.S mi - 592/17.4 S87h7.4 51)l - 0/23.0 0/23.0 0/20.1 0/20.1 0/26.2 - 0/17.5 0/17.S 147/17.2 1w17.3 3G 4G SUG 5TG - - - - 13/10.7 - 6s 13/10.7 Om. 5 7s - 8L - 553/16.0 0/16.8 73/14.2 103/14.1 11/12.8 0/16.2 - 8s 184/15.6 184D5.6 184h5.6 0/17.3 0/17.3 0/17.3 -. 500/1s.s Joo/1s.s 300/1S.S 128/1S .S 128/1S. S 128/1S. S 128/1S.S 128DS.5 128/15.5 0/16.3 0/16.3 0/16.3 6H - 37V16.1 0/21.7 0/19.1 0/2s.1 0/17.3 0/18.8 364/15.9 6G - 201/20.3 472/14.6 477/14.9 193/17.9 40S/16.1 S18/16.2 466hS.1 S39/19.2 0/16.1 - 28P4.S Oll6.3 - 14/15.1 0/17.7 0/17.1 471/16.7 109D6.2 - 0/17.2 - Oh6.3 mS.3 - 76/15.9 WlS.7 4S/lS.6 71D5.0 63/13.4 63/14.S - - 176/15.3 17S/lS.7 - 172/16.0 176D6.2 148/16.S lO/ll.l - 50/12.8 - 0i18.4 0/19.8 u D 357/1S.8 8H - 410/15.7 0121.7 o/ig.o 0/24.4 0/17.4 0/21.5 oiia.9 0/24.1 0/17.6 ni - 0/17.0 0/17.3 363/15.2 - - 182/lS.8 19/15.1 148/15.4 7G 8G - - 464/1S.1 471/15.1 0/16.3 W16.3 7/1S.3 W15.4 7VlS.O 94/1S.O 148/16.S 132/16.6 SO/l2.7 - 28/12.6 0/16.l 0/16.6 t: c c i; c f: L c t:
L c c b - i ii L r D-1 Appendix D. CALCULATIONS OF NUCLEAR AND FOSSIL PLANT COMPETITION BASED ON ECONOMICS M. R. Shay, D. R. Haffner, W. E. Black, T. M. Helm, W. G. Jolly, R. W. Hardie, and R. P. Omberg Hanford Engineering Development Laboratory In a series of calculations that preceded those reported in Chapter 6 for nuclear power systems, the same analytical model was used to evaluate power systems that include both nuclear power plants and coal-fired power plants, with the two types of plants being in economic competition. As was stated in Chapter 6, the results of these calculations indicated that at U3O8 prices above $160/lb, nuclear power plants do not compete well for the assumptions used in this study. Therefore, for the all-nuclear systems it was decided to limit the uranium resources to those available at prices below $160/lb. This appendix describes the initial set of calculations. The nuclear plants used were LWRs, with and without recycle, and they correspond to Cases lL, 2L,. . . .8L in Chap- ter 6. The primary differences between the calculations presented in Chapter 6 (and in Appendix C) and the calculations described here are as follows: (1) Instead of a nuclear energy growth projection, a total electrica projection was used. energy growth (2) In addition to nuclear plants, coal plants were available to satisfy the total electrical energy demand. (3) No price constraint on ore existed. Instead it was assumed that additional uranium ore was always available at increasingly higher costs. As with the all-nuclear systems, two different U308 price structures were used. Table D-1. (4) Power plant selection was based on economics instead of U308 utilization. The electrical energy demand that was used for these calculations is shown in This projected demand assumes a 5.6% per year growth rate until 1980, and a 5.1% per year growth rate from 1980 to 1990. The growth rate decreases each decade until year 2030, after which a constant 2.5% per year growth rate is assumed. The marginal cost of uranium as a function of the cumulative quantity mined was shown in Table B-7 of Appendix B. In this appendix cases that use the high-cost uranium supply are denoted as cases lL, 2L, ..., while cases that use the intermediate-cost uranium supply are denoted as cases lLU, 2LU, .... As has already been emphasized, it was assumed for these calculations that the quantity of available uranium was unlimited. The only
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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 - 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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Page 261 and 262: t a APPENDICES
Page 263 and 264: A-3 Appendix A. ISOTOPE SEPARATION
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Page 283 and 284: i; 1 t u 1 1 B-3 Table 8.5. Reactor
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Page 289 and 290: Appendix C. DETAILED RESULTS FROM E
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Page 293 and 294: L c-5 The introduction of the class
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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)
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