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6-34 1HE LWR WITH FISSILE UUNIUM PCYCLE AND PLUTONIUM THROWAWAY WXIMUM ANNUAL RfWIREMENlS: lNTERMEDlATE COST U$B SUWLV 160. I$Sl BELOW S1M LO, ENRICHMENT - im . iB A i Fig. 6.2-17. The Effect on the Nuclear Fig. 6.2-18. The Effect of the U308 Contribution of LWRs Operating with Fissile Uranium Recycle and Plutonium Throwaway (High-Cost U308 Supply). -32.0 ST U30e Supply on the Nuclear contribution of LWRs Operating with Fissile Uranium Recycle and Plutonium Throwaway (Case 4L). HEDL 7805-090.33 Fig. 6.2-19. Utilization and Movement of Fissile Material in a Nuclear System Consisting of LWRs Operating with Fissile Uranium Recycle and Plutonium Throwaway (Case 4L, High-Cost U308 Supply) (Year 2035). L L
L L L rI i t b c L h: 6-35 238U comprises 57%. The principal advantage associated with this option is that all nuclear units can be located outside the energy centers, which means that the amount of fissile plutonium in fresh fuel that must be handled in this system is zero. without cost, however; it requires the development of an industry capable of reprocessing significant quantities of fuel containing thorium and refabricating significant quantities of fuel containing 232U. In order to successfully implement this option, one must develop a nuclear industry in which approximately 95% of the reprocessing capacity in the year 2035 is capable of handling fuel containing thorium and 57% of the fabrication capacity is capable of handling fuel containing 232U. This advantage is not In sumary, if employed judiciously, a converter strategy based on the LWR can be developed which can discard all fissile plutonium and still supply a maximum nuclear contribution of 590 GWe with a U3O8 supply of 3.0 million ST below $160/lb. This is essentially identical to that of the classical LWR plutonium recycle with the same U308 supply. With a U308 supply of 6.0 million ST below $160/lb, the system could supply a maximum nuclear contribution of 980 GWe; however, as pointed out above, considerable development work would be required on fuel design and fabrication. 6.2.4. Converter System with Plutonium Production Minimized; Pu-~o-~ 33U "Transmutation" An inherent disadvantage in the plutonium throwaway option discussed above is that the fissile plutonium produced in the system is never utilized. Therefore, it was considered de- sirable to analyze an option in which fissile plutonium produced in a similar system is used to produce 233U for the dispersed reactors. The 233U producer would be a converter with a plutonium-thorium core. This converter would, of course, be located in an energy center, while the other reactors would be located outside the center as shown in Fig. 6.1-3 (Option 5U). It is important to note that while this option utilizes all the plutoniun produced in the system, it minimizes the amount of pZutoniwn that is produced. This requires the development of reactor concepts designed specifically to minimize plutonium production. The nuclear contribution of this option utilizing LWRs only (Case 5UL) reaches a maximum of approximately 700 GWe shortly before year 2030 (see Fig. 6.2-20). Thus, utilizing the plutonium produced in the system increases the maximum nuclear contribution by approximately 100 GWe over that of the option with plutonium throwaway; it also produces a delay in the maximum of about eight years (compare with Fig. 6.2-17). The maximum annual u& and enrichment requirements for this option are 75,000 ST/yr and 65 million SWUlyr, respectively, each being approximately 6% less than that required for Option 4. The amount of the system's installed nuclear capacity that must be located in the energy center is shown in Fig. 6.2-21 as a function of time. This option is distinguished by the fact that the maximum capacity that must be located in a secure region does not exceed 100 GWe at any time during the planning horizon. The amount that may be located outside the
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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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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
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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
Page 174 and 175: SWU SWU 6-14 UZJS USILEINS WYI U5IL
Page 176 and 177: 6-16 n nM MEDL nows.1 Option 4: In
Page 178 and 179: 6-18 HM HEDL7OOl.70.3 Option 6: In
Page 180 and 181: SRCIFIED CONSTRUCTION LlMllLD INTRO
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Page 184 and 185: 6-24 The potential nuclear contribu
Page 186 and 187: %- f $400 J 2 s 2, 1 THE LWR FOLLOW
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 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 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
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Page 239 and 240: 7-29 7.4. ADEQUACY OF NUCLEAR POWER
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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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