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i resulting ratios of 41K/39K abundance as measured by the mass spectrometer were, respectively, 0.07 (the natural abundance), 0.02 and 4. The abundance ratio of 4 A-18 corresponds to a more than tenfold enrichment of '+lK. In addition to potassium ions, work has been done on neon, argon, xenon and uranium toward resolving the ion cyclotron resonances for individual positive ions. The work with uranium is proceeding toward estimates of realistic operating parameters (ion densities, magnetic field strength, isotopic excitation energies, device length, ion temperatures, and collector types). A second process involves the achievement of a UF6 plasma by chemi-ionization. UF6 molecules are accelerated by expansion with an inert carrier gas through a supersonic jet. A cross beam of alkali metal molecules results in the formation of NA' or Cs' and UF6'. A radio-frequency quadrupole mass filter deflects the 238UF6 out of the plasma beam, permitting the separation of the two isotopes by collection of the two beams on separate baffles cooled by liquid nitrogen. This process seems to have less potential than the first. Comparison of Advanced Separation Processes The estimated costs of the processes mentioned are compared in Table A-3 with that of gaseous diffusion. With two exceptions, the table is based on process evaluations made by the Nuclear Division of the Union Carbide Corporation17 for ERDA. For the exceptions, which are the FRG's separation nozzle and South Africa's stationary-walled centrifuge, the comparison is based on published statements by the developers of the process. Of all the processes listed, only the costs for the centrifuge, and possibly for the separation nozzle, are known with any degree of certainty . I r; c L L
i i d .- I . ii hi L i: i t ' Li 1 i" A-19 Table A-3. Comparison of Process Economics Specific Operating costs Capital Power Other Than Investment cost Power Cen tri f uge > < > Separation Nozzle' < > c Stationary-Wal led Centrifuge* - - ? LIS-Atomi c < < > LIS-Molecul ar Ch. Exchange: U1"(aq)-UV1(org) Other Aerodynamic Processes > > < > < 7 Plasma: Chemi-ionization > < > Plasma Ion Enrichment (Dawson Process) < < > *Based on estimates made by the process developers. - DEFINITION OF SYMBOLS: - Approximately equal to the diffusion process. >,< ? Unknown. Greater than or 'less than the diffusion process, respectively. References for Appendix A 1. E. 6. Kiser, Jr., "Review of U.S. Gas Centrifuge Program," AIF Fuel Cycle Conf. '77, Kansas City, Mo. (April 1977). 2. USAEC, "AEC Gaseous Diffusion Plant Operations," 0R0-684 (Jan. 1972). 3. H. D. Smythe, Atomic Energy for Military Purposes, Princeton University Press, Princeton, N.J., Aug. 1945. 4. W. E. Groth, K. Beyerle, E. Nann, and K. H. Welge, "Enrichment of Uranium Isotopes by the Gas Centrifuge Method," 2nd Int'l. Conf. on the Peaceful Uses of Atomic Energy, Geneva , Switzerland (Sept . 1958). 5. J. Los Kistemaker and E. J. Z. Veld Huyzen, "The Enrichment of Uranium Isotopes with Ultra-Centrifuges," 2nd Int'l. Conf. of the Peaceful Uses of Atomic Energy, Geneva , Switzerland (Sept . 1958). 6. G. Zippe, "The Development of Short Bowl Ultra Centrifuges," ORO-315 (June 15, 1960). 7. K. Cohen, The Theory of Isotope Separation, McGraw-Hill Book Company, New York, 1951.
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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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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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Page 261 and 262: t a APPENDICES
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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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Page 307 and 308: L L L L [i i” Table D -2. Maximum
Page 309 and 310: Fig. D-2 (cont.) 25W I I I I I (I)
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