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7-40 7.4.6 Conclusions From the preceding discussion and the results presented in Chapter 6 and Appendix C, the following conclusions may be drawn concerning the reactor options, the fuel cycle options, and the U308 supply cases analyzed for this study. the conclusions are tentative and may be changed as a result of different demand growth projections or more accurate or improved reactor characterizations. It should be emphasized that If nuclear power systems were limited to the once-through cycle, it would be necessary to utilize U308 sources at above $160/lb sometime between year 2009 and year 2035 in order to satisfy the projected nuclear power capacity demand. If nuclear power systems were limited to the once-through cycle and to U& supplies below $160/lb, the U.S. nuclear power capacity would peak some time between 2009 and 2035. Nuclear power would fail to satisfy the projected nuclear demand during the 10-year period preceding the peak. If improved LWR designs and improved tails stripping techniques were implemented, the peaks would occur 10 to 15 years later. If the high-cost U308 supply is assumed (3 million ST below $160/lb), all once-through systems, regardless of the converter type employed, result in approximately the same maximum installed nuclear capacity. U nuclear power supply on the once-through cycle. For less-restrictive supply assumptions, advanced converters have time to increase the total Thermal recycle systems have the capability of substantially reducing requirements for U308 or of increasing the maximum installed capacity over the capacity of the once-through cycle. The best thermal recycle systems can support over twice the maximum instal led capacity of the once-through cycle, and, under the intermediate- cost U308 supply assumption (6 million ST below $160/lb), they can fully support the assumed nuclear power growth through year 2050. The systems including breeders have the capability of substantially reducing the mining requirements and/or increasing the maximum instal led capacity beyond thermal systems with recycle. This capability is needed to satisfy the nuclear capacity demand through year 2050 under the high-cost uranium supply assumption (3 million ST below $160/lb). Thermal recycle systems including denatured 233U reactors have the capability of supporting more nuclear capacity than the thermal P U / ~ ~ recycle ~ U systems. achieving this capability would usually require Pu utilization. However, From a resource utilization point of view, nuclear power systems utilizing denatured 2330 reactors can be started equally well with MEU(235)/Th or Pu/Th fuels, providing the eventual use of the plutonium generated in the MEU(235)/Th cycle is assumed.
L e, I I ' lb t 7-41 Systems that use breeders (i.e., fast transmuters) to produce 233U for LWRs or advanced converters operating on denatured 233U fuel have a capability comparable to systems employing the classical Pu/U breeder cycle to satisfy the assumed demand through 2050 with the U308 resource base assumed in this study. Section 7.4. References 1. John Klemenic, Director, and David Blanchfield, Mineral Economist, Supply Analysis Division, Grand Junction Office, DOE Uranium and Enrichment Division, in paper entitled "Production Capability and Supply," paper presented at Uranium Industry Seminar, October 26-27, 1977, Grand Junction, Colorado; proceedings pub1 ished as GJO-l08( 77).
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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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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 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
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Page 293 and 294: L c-5 The introduction of the class
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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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