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2-1 0 the denatured cycle, a condition of mutual dependence between the dispersed reactors and the energy-center reactors is created. Thus while nations choosing to operate only denatured (i .e. , dispersed) reactors must obtain their fuel from nations that have energy-center transmuters, the nations operating the transmuters will in turn rely on the nations operating dispersed reactors for their tvansmuter fuel requirements (Pu). Hence, in addition to the possible nonproliferation advantages of the denatured fuel cycle, the concept also introduces a greater flexibility in national energy policies. , References for Chapter 2 1. H. A. Feiveson and T. B. Taylor, "Security Implications of Alternative Fission Futures," BUZZ. Atomic Scienthts, p. 14 (Dec. 1976). 2. "A Report on the International Control of Atomic Energy," prepared for the Secretary of State's Committee on Atomic Energy by a Board of Consultants: Chester I. Barnard, Dr. J. R. Oppenheimer, Dr. Charles A. Thomas, Harry A. Winne, and David E. Lilienthal (Chairman), Washington, D.C., March 16, 1946, pp. 127-213, Department of State Pub- lication 2493. 3. "Nuclear Energy Center Site Survey - 1975," Volumes 1-5, NUREG-0001, Nuclear Regulatory Commi ssi on , January , 1 976. 4. "Regional Nuclear Fuel Cycle Centers," 1977 Report of the IAEA Study Project, STI/TUB-445, International Atomic Energy Agency, 1977.
e Isr i L i- b t CHAPTER 3 ISOTOPIC CHARACTERISTICS OF DENATURED 233U FUEL Chapter Out1 ine 3.0. Introduction, T. J. Burns and L. S. Abbott, ORNL 3.1. 3.2. Estimated 232U Concentrations in Denatured 233U Fuels, D. T. Ingersoll, ORNL Radiological Hazards of Denatured Fuel Isotopes, H. R. Meyer and J. E. Till, ORNL 3.3. Isotopics Impacting Fuel Safeguards Considerations 3.3.1. 3.3.2. Enrichment Criteria of Denatured Fuel, c. M. Newstead, BNL Fabrication and Handling of Denatured Fuel, J. D. Jenkins and 3.3.3. 3.3.4. R. E. Brooksbank, ORNL Detection and Assay of Denatured Fuel , D. T. Ingersoll, ORNL Potential Circumvention of the Isotopic Barrier of Denatured Fuel, E. H. Gift and W. B. Arthur, ORGDP 3.3.5. Deterrence Value of 232U Contamination in Denatured Fuel, c. M. Newstead, ORNL
Page 1 and 2: Interim Assessment of the Denatured
Page 3: i L i b I, i L L bi L L Contract No
Page 7 and 8: 1, L L t i Ltr 1 L L V PREFACE AND
Page 9 and 10: L i Li 1, I b k b id ii t L id b i
Page 11 and 12: I L bi i; L 7.3.1. Possible Procedu
Page 13 and 14: i xi I b L ABSTRACT A fuel cycle th
Page 15 and 16: I b .- i, hd t t CHAPTER 1 INTRODUC
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Page 19 and 20: L .- k id .- I L: _ - I iclr .- i b
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Page 23 and 24: huJ -- AI I ' b --- I bl --- t L L
Page 25 and 26: -- t Li - I' b -. c (u I i ai L i i
Page 27 and 28: L - i' u i Lt L r- L t- b L 2-7 den
Page 29: 2-9 1. Nuclear power is limited to
Page 34 and 35: 232" Fig. 3.0-1. Decay of 232U. ORN
Page 36 and 37: 3-6 3.1. ESTIMATED U CONCENTRATIONS
Page 38 and 39: 3-8 The values in Table 3.1-2 are a
Page 40 and 41: 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
Page 66 and 67: introduce time, cost and visibility
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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_- 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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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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