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50- 40 6-22 c Y \ VL - :-: F 30- - LWR-LEU c, V 0 : 20 n - FBR - c, I- 0 10 0 ORNL-DWG. 78-14830 I I I I 1 I I - - - - I I 1 I I I I 50 100 150 200 u308 Price. $/lb 250 300 350 400 Fig. 6.1-8. Influence of U3O8 Prices on Total Power Costs. ONCE-THROUGH OPTION u30e PRICE, SAB HEDL 7805-090.39 Fig. 6.1-9. Total Power Cost of Various Reactor Systems as a Function of U308 Price (Constant U30s Price with Time; Once-Through Option). 3 '! G I c c
_ _ t b Mxx) I? li 6-23 6.2. DISCUSSION OF RESULTS FOR SELECTED NUCLEAR POLICY OPTIONS This section discusses results obtained in this study for a selected set of nuclear system options that typify the role of nuclear power under different nuclear policy decisions. The intent is to identify the basic issues, to determine the logical consequences of decisions made in accordance with those issues, and to display the consequences in an illustrative manner. Section 6.1 are presented in Appendix C. Detailed results for all the nuclear system options outlined in 6.2.1. The Throwaway/Stowaway Option The throwaway/stowaway cycle (see Fig. 6.1-1) is a conceptually simple nuclear system option and therefore has been selected as the reference cycle against which all other op- Avg. Capacity Factor = 0.67 Tails Ccmmosition - 0.W20 - r n $ m - HTGR Fig. 6.2-1. Lifetime U308 Requirements for Various Reactors on the Throwaway Cycle. -1 tions are compared. ly understand the implications of the throwaway cycle, the effect of several deployment options utilizing the various advanced converters on the throwaway cycle was analyzed in detail. In general, the analysis assumed a nuclear growth rate of 350 GWe in the year 2000 followed by a net increase of 15 GWelyr, but the consequences of a significant reduc- tion in the nuclear growth rate were also considered. In addition, the effect of both the high-cost and the intermediate-cost U308 supplies was determined. In order to thorough- A summary of the 30-yr U308 requirements for several reactors on the throwaway cycle, including an LWR with a fuel system designed for an extended discharge exposure, is shown in Fig. 6.2.1. In each case, the average capacity factor of the reactor was assumed to be 0.67, and the tails composi- tion of the enrichment plant was assumed to be 0.0020. As the figure indicates, all the reactors have lower U308 requirements than the standard LWR, the extended-discharge LWR being 6% lower, the SSCR 16% lower, the HTGR 23% lower, and the slightly enriched HWR 39% lower. These U308 requirements were calculated for essentially standard designs without elaborate. design optimization. performance characteristics; however, the goal of this analysis was not to delineate the ultimate role of any particular reactor concept based on current performance characteristics, but rather to identify the probable role of each reactor concept and the incentive for improving its performance characteristics. It i s recognized that design optimization could improve the reactor
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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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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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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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Y m I I I . aro ID0 10.00 4-5 ORNL-
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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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Page 138 and 139: ! 5-4 5.1. REACTOR RESEARCH AND DEV
Page 140 and 141: 5-6 As has been pointed out above,
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Page 144 and 145: 5-10 The fuel performance program u
Page 146 and 147: . 5.1.2. Government Research and De
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Page 152 and 153: I DATA BASE DEMu)pMENT DEMO DESIGN
Page 154 and 155: j ~ 5-20 The R,D&D costs are highes
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Page 160 and 161: 5-26 program, including hot testing
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Page 164 and 165: 6-4 persed areas ensured - a fact w
Page 166 and 167: 6-6 6.1.2. Reactor Options The reac
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Page 170 and 171: 6-10 6.1.3. Nuclear Policy Options,
Page 172 and 173: Table 6.1-4. Nuclear Policy Options
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Page 176 and 177: 6-16 n nM MEDL nows.1 Option 4: In
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Page 180 and 181: SRCIFIED CONSTRUCTION LlMllLD INTRO
Page 184 and 185: 6-24 The potential nuclear contribu
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Page 188 and 189: 141.6 ST - U308 4 7.2 lo3 swu ENRIC
Page 190 and 191: 6-30 reactor. Since this increase i
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Page 194 and 195: 6-34 1HE LWR WITH FISSILE UUNIUM PC
Page 196 and 197: THE LWR WITH PURONIUM MlNUllUTlON A
Page 198 and 199: 6-38 be located in energy centers a
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Page 204 and 205: 6-44 6.2.7. Converter-Breeder Syste
Page 206 and 207: 25.2 ST swu 6-46 19 Kg fir Pu 13 Kg
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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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
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t a APPENDICES
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A-3 Appendix A. ISOTOPE SEPARATION
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I] 1- $i ill 8 LI b' The Gas Centri
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id A- 7 The Component Preparation L
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i ?L 1- U t L fl bi L c u La -- ti
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p; ‘U i-- L ,c c Japan A-1 1 Tabl
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13 A-13 L" efficient of the units d
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L L L t I h h u L; _- t f is throug
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u A-1 Aerodynamic Methods 7 Both th
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i i d .- I . ii hi L i: i t ' Li 1
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la t L I I, lj ir 1 Li c I L L' B-1
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i; 1 t u 1 1 B-3 Table 8.5. Reactor
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Table 6-7. Marginal Costs of U308 a
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LJ L L1 a .E 4' P Y W 5 18 2 16 : 0
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Appendix C. DETAILED RESULTS FROM E
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1 i; Li b L lkd t L L I hd I ' L; i
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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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