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- To Vacuum Pump Molecular Pump Casing Heavy Fraction A-6 rv Light Fraction -' If uF6 Feed Magnet / Suspension Stationary Magnet \ Bearing Fig. A-1. ZIPPE Centrifuge (Simplified). Spinning Magnet Damper scoop Rotor Baffle P1 ate scoop Drive Motor The Equipment Test Facility (ETF) was conceived to provide for the reliability testing of "high capacity" centrifuges. This facility, which began operation in 1971, has been the source of reliability testing for two generations of machine designs. Many of the first generation high capacity machines are still operating in this facility. L c L L L
id A- 7 The Component Preparation Laboratories (CPL) in Oak Ridge, Tennessee and Torrance, California, were built to evaluate, improve and demonstrate techniques amenable to the mass production for manufacturing centrifuges. This facility became operational in early 1974. The Component Test Facility (CTF) was designed to demonstrate the machine reliability and operability testing of substantial numbers of centrifuges in a cascade operation. Construction was begun in 1972 and the first phase of startup of the facility was completed in January 1977 with cascade operation of about one-half of the machines operating. The remaining machines were operable within a few weeks later. of the CTF is significant, about 50,000 SWU/yr, or about the annual enriching requirement for a 500 MW power reactor. The capacity The Advanced Equipment Test Facility (AETF), in addition to being a reliability test facility will also test the plant subsystems which support the machines. machines to be installed in this facility will have significantly greater separative work capability than those in the CTF. of 1978. The The AETF is expected to be operable in the spring In Europe, the URENCO organization, consisting of participants from England, Germany, and Holland, has a program that so far has been directed toward machine reliability and long lifetime. URENCO is currently producing about 200 MTSWU/yr from plants at Almelo, Holland and Capenhurst, England. Expansion of these facilities is planned by 1982. The URENCO group expects to have 2000 MTSWU/yr in operation, 1300 MTSWU/yr at Almelo, and the remaining 700 MTSWU/yr at Capenhurst. The Becker Separation Nozzle The Becker process,9 being developed in Germany by Dr. E. W. Becker and his associates, uti1 izes the pressure gradient developed in a curved expanding supersonic jet to achieve separation in a gas mixture. The separation nozzle stage is shown schematically in Fig. A-2. A light gas, helium or hydrogen, is added to the UF6 in order to increase the velocity of the jet. As the expanding jet traverses the curved path, the heavier component is enriched in the vicinity of the wall. A knife edge divides the jet into two fractions--one enriched in the light component, and the other enriched in the heavy component--which are then pumped off separately from the stage. A1 though the separation obtained per stage is relatively high (~1.025)~ many separation nozzle stages are needed to obtain an appreciable enrichment. This process avoids the problems associated with the fine-pored membrane required for gaseous diffusion, and those associated with the high-speed rotating parts of the gas centrifuge. It does suffer, however, from the disadvantage of a relatively high power requirement, primarily because a great deal of light gas must be recompressed between stages along with the UF6 process gas.
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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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Page 261 and 262: t a APPENDICES
Page 263 and 264: A-3 Appendix A. ISOTOPE SEPARATION
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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
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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 303 and 304: Qulatiw klur W i t y hilt (*I thrmg
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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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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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