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1 8. W. R. Voigt, "Enrichment Policies," AIF Fuel Cycle Conf. '77, Kansas City, Mo. (April 1977). 9. E. Von Halle, "Summary Review of Uranium Isotope Separation Methods Other Than Gaseous Diffusion and Gas Centrifugation," ORO-690 (Feb. 23, 1972). 10. A. J. A. Roux and W. L. Grant, "Uranium Enrichment in South Africa," presented to European Nuclear Conference, Paris, France (Apri 1 1975). 11. Nuclear News, p. 80 (June 1977). 12. S. Blumkin, "Survey of Foreign Enrichment Capacity, Contracting and Technology: Jan. 1976-Dec. 1976," K/OA-2547, Pt. 4 (April 18, 1977). A-20 13. Letter, R. J. Hart, ERDA-ORO, to W. R. Voigt, ERDA-HQ, "Interim Uranium Enrichment Long-Range Operating Plan," (August 9, 1977). 14. M. Benedict, et al., "Report of Uranium Isotope Separation Review Ad Hoc Committee," 0R0-694 (June 2, 1972). 1 15. Allas S. Krass, "Laser Enrichment of Uranium: The Proliferation Connection,' -' Science Vol. 196, No. 4291, p. 721-731 (May 13, 1977). i 16. J. M. Dawson, et al., "Isotope Separation in Plasmas Using Ion Cyclotron Resonance," TRW Defense & Space Systems, Redondo Beach, Calif. 17. p. R. Vanstrum and S. A. Levin, "New Processes for Uranium Isotope Separation," IAEA-CN-36/12 (11.3), Vienna, Austria (1977). i: I: I; I'
la t L I I, lj ir 1 Li c I L L' B-1 Appendix B. ECONOMIC DATA BASE USED FOR EVALUATIONS OF NUCLEAR POWER SYSTEMS M. R. Shay, D. R. Haffner, W. E. Black, T. M. Helm, W. G. Jolly, R. W. Hardie, and R. P. Omberg Hanford Engineering Development Laboratory The economic data base used in .the assessment of the impact of denatured fuel cycles in the various nuclear systems options described in Chapter 6 was jointly developed by Combustion Engineering, Oak Ridge National Laboratory, United Engineers and Constructors, Argonne National Laboratory, Resource Planning Associates, Hanford Engineering Development Laboratory, DOE Division of Uranium Resources and Enrichment, and DOE Division of Nuclear Research and Applications. The data base includes capital costs, operation and maintenance costs, fuel fabrication and reprocessing costs, capacity factors, money costs, and uncertainties. The deflated and present-valued capital costs for LWRs, SSCRs. HTGRs, CANDUs, and FBRs, excluding interest during construction, are shown in Table B-1. including interest during construction are shown in Table B-2. The same capital costs In either case, the stream of expenses incurred during the construction of the plant is discounted to the date of startup and is measured in dollars of constant purchasing power. The uncertainty ranges included in Table 8-2 represent current best estimates of the most probable variations in capital costs. For flexibility, the uncertainties are expressed relative to the reference LWR capital cost. Table B-1. Capital Costs of Power Plants Excluding Interest During Construction The operation and maintenance costs for the same power plants are shown in Power Plant Type Costs ($/kWe)* Table 6-3. The higher costs for the SSCR and the CANDU over the standard LWR are due LWR 500 to the heavy water replacement requirement SSCR 520 + 39 (for D20) = 558 and the necessity for performing some HWR HTGR 605 t 156 (for D20) = 761 560 to 580 maintenance in atmospheres containing tritium. Additional minor reactor costs FBR 625 to 875 are given in Table 8-4. * Based on 7/1/76 dollars. Table B-2. Captial Costs of Power Plants Including Interest During Construction Power Plant TY Pe cost ($/kWe)* Cost Re1 ative to LWR Cost cost Uncertainty LWR 625 95% to 105% reference cost SSCR 650 + 40 (heavy water) = 690 +lo% 105% to 120% of LWR cost HWR 755 + 160 (heavy water) = 915 +46% 120% to 150% of LWR cost HTGR 71 5 +14% 105% to 125% of LWR cost FBR 800 +28% 125% to 175% of LWR cost *Based on 1/1/77 dollars.
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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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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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-- - . & 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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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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