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I .o v) t- z W W 0.9 = U - 3 0 W a 0.8 Om rr) 3 W 2 0.7 l- a -I W U 4-34 0.6 0 0.7 0.8 0.9 1.0 1.1 I .2 1.3 1.4 1.5 1.6 INITIAL 235U ENRICHMENT, % Fig. 4.3-1. Fuel Utilization Characteristics for Enriched-Uranium-Fueled CANDU. 4. annual U308 makeup requirements at near-equilibrium are about 27 ST/GWe for the 16,00&MWD/T burnup case. HEU/Th, U Recycle: With 93% 235U-enriched uranium startup and makeup, the This net consumption of U308 i s only 14% o f the LWR once-through cycle and 28x of the LWR thorium cycle (see Cases A and J in Table 4.1-1). U308 requirement is more than double that of the CANDU slightly enriched uranium cycle. In addition, the transition to equilibrium and the out-of-core inventory requirements, de- pending on the recycle turn-around time, can be very significant. 1 However, the initial core 5. Denatured U/Th, U Recycle (233U Makeup): The initial core 233U inventory requirement is about 1,650 kg/GWe, with an annual net requirement of about 100 kg 233U/GWe. 6. MEU/Th, U Recycle (235U Makeup): The initial core requirement is about the same as that for the standard thorium cycle (i.e., HEU/Th cycle); however, the equilibrium net U308 consumption is slightly increased. 7. MEU/Th, No Recycle: This cycle option is included to indicate that recycle of the self-generated 233U is advisable for the MEU/Th c.ycle.. The lifetime U308 requirement for the once-through MEU/Th cycle is about 8,300 ST, which is a factor of 2.3 higher than that for the once-through enriched-uranium cycle in CANDU reactors.
F-- I iJ L ii - L c c 4-35 References for Section 4.3 1. J. S. Foster and E. Critoph, "The Status of the Canadian Nuclear Power Program and Possible Future Strategies," Annals of Nuclear Energy 2, 689 (1975). 2. S. Banerjee, S. !?. Hatcher, A. D. Lane, t!. Tam and J. I. Veeder, "Some Aspects of the Thorium Fuel Cycle in Heavy-t!ater-Moderated Pressure Tubes Reactors ,I' ~ucl. Tech. 34, 58 (1977). 3. E. Critoph, S. Banerjee, F. \l. Barclay, C. Hamel, M. S. Milgram and J. 1. Veeder, "Prospects for Self-Sufficient Equilibrium Thorium Cycles in CAMDU Reactors," AECL-5501 (1 976). 4. C. E. Till, E. 11. Bohn, Y. I. Chang and J. 6. van Erp, "A Survey of Considerations Involved in Introducing CANDU Reactors into the 1I.S. ,I1 ANL-76-132 (January 1977). 5. Y. I. Chang, C. E. Till, R. R. Rudolph, J. R. Deen, and M. J. King, "Alternative Fuel Cycle Options: Performance Characteristics and Impact on Nuclear Power Growth Potential ,'I "-77-70 (Sept. 1977). ,' , ,
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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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huJ -- AI I ' b --- I bl --- t L L
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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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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
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Page 75 and 76: Y m I I I . aro ID0 10.00 4-5 ORNL-
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Page 81 and 82: _- I -- L i d .-- L 4-1 1 Reference
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Page 87 and 88: u -- x i I*i 1- bi 4-1 7 The use of
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Page 91 and 92: 4-21 Case B" is a modification of C
Page 93 and 94: c 4-23 L i a L L 4.2. SPECTRAL-SHIF
Page 95 and 96: 4-25 Initial analyses of spectral-s
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Page 99 and 100: c- i L L e I b 4-29 . safeguards fo
Page 101 and 102: L t i- bi L L t i 4-31 a significan
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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
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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/
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Page 125 and 126: Table 4.6-1. Comparison of Fuel Uti
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Page 140 and 141: 5-6 As has been pointed out above,
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Page 146 and 147: . 5.1.2. Government Research and De
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Page 152 and 153: 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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