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5 4 17 E 16 15 - - - I 8-6 ''111 REACTOR OPTIONS: LWR SSCR HWR HTGR FER 6 A h h h f l I I I 7, I I I'C I I ,'[I I I I' ff7 HEDL 78M-WO.W Fig. B-1. Sensitivity of Total Levelized Power Cost to Capital, Fabrication, and Reprocessing Cost Uncertainties. the abscissa. The major difference between the two methods of analysis is the u308 price at Which reactor options incur the same total power cost. For example, whereas at a constant U& price the PWR and HWR options have the same power generation cost at * $160/lb U308 for an increasing UJO~ price they have the same cost at * $130/lb U&. From the data shown in Fig. B-1 it is clear that the total power cost for each reactor and fuel cycle option is dominated by uncertainties. The uncertainty effect produces a significant overlap between reactor power costs. In addition, it is evident from Fig. B-2 that fuel costs, viz., U308 prices, also significantly affect not only the levelized power costs but also the competitive relationship between reactor options. Therefore, it is difficult to classify reactors as either more economical or less economical based solely on power generation cost estimates. L I 'I
LJ L L1 a .E 4' P Y W 5 18 2 16 : 0 m 0 4 8-7 I I I I I I (a) U308 price constant over 30-yr reactor life. U308 PRICE, $/lb I I I I I I (b) U308 price increases with rate of consumption. HWR-US(SE)/II \ I I I I I I HEDL 7805-090.16 0 40 60 80 100 120 140 160 U308 PRICE AT STARTUP, $/lb HEDL 78Q545'0.17 Fig. 8-2. Effect of U308 Price on Total Power Cost for Reactors Operating on Throwaway Cycle.
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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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-- 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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Page 239 and 240: 7-29 7.4. ADEQUACY OF NUCLEAR POWER
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Page 243 and 244: x ibd 1 .. I i, L -- i t Table 7.4-
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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
Page 273 and 274: 13 A-13 L" efficient of the units d
Page 275 and 276: L L L t I h h u L; _- t f is throug
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: Table 6-7. Marginal Costs of U308 a
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
Page 299 and 300: -, ii I ; b i- ii L b 4 i L L i‘
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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