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5. 7. 8. 9. 10. 4-22 Letter from P. A. Hatzie (Combustion Engineering) to H. B. Stewart (Nuclear Technology Evaluations Company), ''U,O, Requirements in LllRs and SSCRs," July 25, 1977. Letter from I?. A. Hatzie (Combustion Engineering) to J. C. Cleveland (ORNL), Wass Balances for Various LWF? Fuel Cycles," Hay 1977. "Quarterly Progress Report for Fourth Quarter vi'-77, Thorium Assessment Program," Combustion Engineering. "P:uclear Power Growth 1974-2000,'' Office of Planning and Analysis , U.S. Atonic Energy Comission, I!P,SH 11 39( 74) , (February 1574). "Assessment of Uti1 ization of Thorium in BWRs ,I' ORNL/SUB-4380/5, NEGD-24073 (January 1978). "Monthly Progress Report for August 1978, NASAP Preliminary BWR Uranium Utilization Improvement Evaluations," General Electric Co. "Appraisal of BWR Plutonium Burners for Energy Centers ,I' GEAP-11367 (January 1976). L L E c L
c 4-23 L i a L L 4.2. SPECTRAL-SHIFT-CONTROLLED REACTORS N. L. Shapiro Combustion Engineering, Inc. The Spectral -Shift-Control led Reactor (SSCR) is an advanced thermal converter reactor that is based on PWR technology and offers improved resource utilization, partic- ularly on the denatured fuel cycle. is designed to minimize the number of reactions in control materials throughout the plant life, utilizing to the extent possible captures of excess neutrons in fertile material as a method of reactivity control. material serves to reduce fuel makeup requirements. The SSCR differs from the conventional PWR in that it The resulting increase in the production of fissile In the conventional PWR, long-term reactivity control is achieved by varying the concentration of soluble boron in the coolant to capture the excess neutrons generated throughout plant life. The soluble boron concentration is relatively high at beginning of cycle, about 700 to 1500 ppm, and is gradually reduced during the operating cycle by the introduction of pure water to compensate for the depletion of fissile inventory and the buildup of fission products. The SSCR consists basically of the standard PWR with the conventional soluble boron reactivity control system replaced with spectral-shift control. Spectral-shift control is achieved by the addition of heavy water to the reactor coolant, in a manner analogous to the use of soluble boron in the conventional PWR. Since heavy water is a poorer moderator of neutrons than light water, the introduction of heavy water shifts the neutron spectrum in the reactor to higher energies and results in the preferential absorption of neutrons in fertile materials. In contrast to the conventional PWR, where absorption in control absorbers is unproductive, the absorption of excess neutrons in fertile material breeds additional fissile material, increasing the conversion ratio of the system and decreasing the annual makeup requirements. At beginning of cycle, a high (approximately 50-70 mole X) D20 concentration is employed in order to increase the absorption of neutrons in fertile material sufficiently to control excess reactivity. Over the cycle, the spectrum i s thermalized by decreasing the D20/H20 ratio in the coolant to compensate for fissile material depletion and fission-product buildup, until at end of cycle essentially pure light water (approximately 2 mole % D20) is present in the coolant. The basic changes required to implement spectral-shift control in a conventional PWR are illustrated in a simplified and schematic form in Fig. 4.2-1. In the conventional PWR, pure water is added and borated water is removed during the cycle to compensate for the depletion of fissile material and buildup of fission-product poisons. The borated water removed from the reactor is processed by the boron concentrator which separates the discharged coolant into two streams, one containing pure unborated water and the second
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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 .- 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
Page 42 and 43: 3-1 2 232u IN RECYCLED HTGR FUEL (p
Page 44 and 45: 3-14 3.2.2 Toxicity of 232Th Given
Page 46 and 47: 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11.
Page 48 and 49: 3.18 There are three approaches whi
Page 50 and 51: 1 i i 3-20 3.3.2. Fabrication and H
Page 52 and 53: The 3-22 3.3.3 Detection and Assay
Page 54 and 55: 3-24 3.3.4. Potential Circumvention
Page 56 and 57: 3-26 - either large centrifuge pilo
Page 58 and 59: ! 3-28 Table 3.3-3. Enriched Proauc
Page 60 and 61: 3-30 The high alpha activity of ura
Page 62 and 63: 3- 32 Table 3.3-7. Sumry of Results
Page 64 and 65: 3-34 statistical redundancy through
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Page 68 and 69: 3-38 An additional factor relative
Page 71 and 72: I b t I t L 1; L t ki 4.0. 4.1. CHA
Page 73 and 74: L L _ _ { i J _- \ I b B u il c _.
Page 75 and 76: Y m I I I . aro ID0 10.00 4-5 ORNL-
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Page 79 and 80: L L; L t -I I ' b L -- t i b -- I;
Page 81 and 82: _- I -- L i d .-- L 4-1 1 Reference
Page 83 and 84: _- id L t I , 4d i, L id L 5 bi t h
Page 85 and 86: -- - . & I I ' h I ' Y 61 L -- I( L
Page 87 and 88: u -- x i I*i 1- bi 4-1 7 The use of
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Page 91: 4-21 Case B" is a modification of C
Page 95 and 96: 4-25 Initial analyses of spectral-s
Page 97 and 98: h 1' b t c i--; & I- & 1: i f 4-27
Page 99 and 100: c- i L L e I b 4-29 . safeguards fo
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Page 103 and 104: ~ kc'l c" -1 r-"! r! r-'i c Table 4
Page 105 and 106: F-- I iJ L ii - L c c 4-35 Referenc
Page 107 and 108: c r- L i] L h L __ f; t 4-37 trons
Page 109 and 110: Table 4.4-1. Fuel Utilization Chara
Page 111 and 112: L I 1 I Ld I ie i-- 1 t' 4-41 4.4.2
Page 113 and 114: 4-43 Table 4.4-4. PBR Coated Partic
Page 115 and 116: HEU/Th 0.59 Seed i3 Breed 0.58 HEU/
Page 117 and 118: L i; 1 I i; i 1. 2. 3. 4. 5. 6. 7.
Page 119 and 120: 4-49 Table 4.5-1. Fuel Utilization
Page 121 and 122: ments. 4-51 The calculations for LM
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Page 125 and 126: Table 4.6-1. Comparison of Fuel Uti
Page 127 and 128: 4-57 _I 10 10' 2 2' CASE NUMBER -.
Page 129 and 130: 4-59 Most of the information availa
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Page 133: 4-63 on only the preliminary data p
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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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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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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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