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6-50 (4) If all plutonium produced were transmuted to 233U but no attempt was made to minimize the amount of plutonium produced, the maximum installed nuclear capacity could be as large as 640 GWe with the high-cost U30a supply. As much as 21% o f the installed nuclear capacity would have to be located in secure energy centers, however, and it would require that 34% o f the reprocessing capacity be devoted to fuel containing thorium and 20% of the refabrication capacity be devoted to fuel containing 233U. (5) If a nuclear system utilizing an FBR with a Pu-U core and a thorium blanket were developed, the system could maintain a net addition rate of 15 GWe/yr indefinitely. The installed nuclear capacity, in this case, could be as high as 1100 GWe in year 2050; however, 56% o f this capacity would have to be located in secure energy centers. Also, approximately 38% o f the reprocessing capacity would have to be devoted to fuel containing thorium and 27% of the refabrication capacity would have to be devoted to fuel containing 232U. (6) If a nuclear system utilizing an FBR with a Pu-Th core and a thorium blanket were developed, the maximum installed capacity would depend upon the performance characteristics of the denatured design receiving fuel from the FBR. the nuclear system would be capable of adding 15 GWe/yr indefinitely. design were a denatured LWR, then the installed nuclear capacity would increase to approximately 850 GWe in about year 2035 and decrease thereafter. If this design were a denatured breeder, If, however, the In addition to the results and conclusions presented in this chapter, detailed results for all the nuclear policy options calculated are tabulated in Appendix C. Also, as men- tioned earlier, a separate analysis performed under the assumption of an unlimited U308 supply but with the nuclear power systems in competition with coal-fired plants is described in 1. 2. 3. 4. 5. 6. 7. Appendix D. Chapter 6 References R. D. Nininger, "Remarks on Uranium Resources and Supply," Fuel Cycle 78, Atomic Industrial Forum, New York, March 7, 1978. John Klemenic, Director, Supply Analysis Division, Grand Junction Office, DOE Uranium and Enrichment Division, "Production Capabi 1 i ty , 'I October 1978, John Klemenic and David Blanchfield, Mineral Economist, Grand Junction Office, "Produc- tion Capability and Supply," paper presented at Uranium Industry Seminar, October 26-27, 1977, Grand Junction, Colorado; proceedings pub1 ished as GJO-108( 77). "Uranium Enrichment Services Activity Financial Statements for Period Ending September 30, 1977," p. 13, Schedule C, 0R0-759. "AEC Gaseous Diffusion Plant Operations," 0R0-684, USAEC (January 1972). "Data on New Gaseous Diffusion Plants," 0R0-685, USAEC (April 1972). See also, T. M. Helm, M. R. Shay, R. W. Hardie, and R. P. Omberg, "Reactor Design Characteristics and Fuel Inventory Data," TC-971 , Hanford Engineering Development Laboratory (September 1977). L L L L L L G 1;: L L I:
- id L L -. i Y L L r' . u A- - 7.0. Introduction, T. J. Burns, ORNL CHAPTER 7 OVERALL ANALYSIS OF DENATURED FUEL SYSTEMS Chapter Out1 ine 7.1. Proliferation-Resistant Characteristics of Denatured 233U Fuel , C. M. Newstead, BNL, and T. J. Burns, ORNL 7.1.1. Isotopic Barrier of Fresh Fuel 7.1.2. Gamma-Radiation Barrier of Fresh Fuel 7.1.3. Spent Fuel Fissile Content 7.1.4. Conclusions 7.2. Impact of Denatured 233U Fuel on Reactor Performance and Selection: with Other Fuel Cycles, T. J. Burns, ORNL Comparison 7.3. 7.4. 7.5. 7.2.1. Thermal Reactors 7.2.2. Fast Reactors 7.2.3. Symbiotic Reactor Systems 7.2.4. Conclusions Prospects for Implementation and Commercialization of Denatured 233U Fuel Cycle, J. C. Cleveland and T. J. Burns, ORNL 7.3.1. Possible Procedure for Implementing and Commercializing the Denatured Fuel Cycle 7.3.2. Considerations in Commercializing Reactors Operating on A1 ternate Fuels 7.3.3. Conclusions Adequacy of Nuclear Power Systems Utilizing Denatured 233U Fuel for Meeting Electrical Power Demands, M. R. Shay, D. R. Haffner, w. E. Black, T. M. Helm, R. W. Hardie, and R. P. Omberg, HEDL 7.4.1. The Analytical Method 7.4.2. 7.4.3. Data Base Results for Price-Limited Uranium Supplies 7.4.4. 7.4.5. 7.4.6. Results for Unconstrained Resource Availability Systems Employing Improved LWRs and Enrichment Technology Conclusions Tradeoff Analysis and Overall Strategy Considerations, T. J. Burns and I. Spiewak, ORNL 7.5.1. No-Recycle Options 7.5.2. Recycle Options 7.5.3. Overall Conclusions and Recommendations
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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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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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Page 172 and 173: Table 6.1-4. Nuclear Policy Options
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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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