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! Fuel Element Sheath 0.d. mn Sheath i.d; mn Sheath material Pellet o.d, mn Fuel density, g/cc Fuel material 4-32 Table 4.3-1. CANDU-PHW Design Parameters Bund1 e Number of elements/bundle Length, mn Active fuel length, rm Volume of end plugs, etc., cc Void in end region. cc Coolant in end region, cc Ring 1 No./radius, mm) Ring 2 t No./radius, Ring 3(No./radius, mn Ring 4(No./radius, m Ctiannel Number of bundles Pressure tube material Pressure tube i.d, nun Pressure tube 0.d. mn Calandria tube material Calandria tube i.d, nnn Calandria tube o.d, mn Pitch, nnn Core 7 Number of channels Net MWe Net <strong>the</strong>rmal efficiency, % Operating Conditions D20 purity, % Average pin linear pqer, W/cm Average temperature, C Fuel Sheath Cool ant Moderator Ratural Uranium Thorium System Sys tem 13.075 12.237 Zr-4 12.154 10.36 u02 37 495.3 476.82 54.29 24.14 76.69 1/0.0 6/14.885 12/28.755 18/43.305 12 Zr-lib 103.378 111.498 Zr-2 128.956 131.750 285.75 380 633 29.0 99.75 271.3 936 290 290 68 13.081 12.244 Zr-4 12.154 9.4 Tho2 37 495.3 475.4 65.68 34.99 66.43 1/0.0 6/14.884 12/28.753 18/43.307 12 Zr-Nb 103.400 111.782 Zr-2 129.200 131.740 285.75 728 1229 29.7 99.75 269.3 850 293 293 57 L L G G c I 7 Li
~ kc'l c" -1 r-"! r! r-'i c Table 4.3-2. Fuel Utilization Characteristics for CANDUs Under Various Fuel Cycle Optionse Equilibrium Cycle Net Fissile Consumption U,O, Requirement Initial Fissile Fissile Ffssile Fissile Initial Inventory Charge Discharge Enrichmentb Burnup Annual Lifetimeg Loading Annual Lifetime Fuel Type (kg/GWe) (kg/GWe-yr) (kg/GWe-yr) (% HM) (Mh'D/kg m) (kg/GWe-yr) (kg/GWe) (ST/GWe) (ST/GWe) (ST/GWe) Natural U. 897 235U 852 235U no recycle Slightly enriched 1261 235U 561 235U U. no recycle MEU/Th, 2121 235U 1052 235U no recycle MEU/Th, 2121 235U 250 235$ U recycle 685 233U . Denatured 1648 233U 831 233U 23 3U02/Th02, U recycle LEU, 897 235U 399 235U U + Pu recycle 378 Puf 168 Puf HEU/Th. U recycle 2159 235U 191 235Uf 750 233U 249 235Uc 340 Puf 59 23 5u= 183 Puf 336 235Uc 25 Puf 476 233U 99 235Ud 30 Puf 685 233U 729 233U 32 Puf 61 235p 197 Puf 86 235Uf 2 Puf 750 23311 Dispersible Resource-Based Fuels 0.71 1 7.5 603 235U -340 Puf 1.0 16 502 235U -183 Puf 25605 235U 164 ,-lo200 Puf 17530 235U 257 -5490 P u ~ 1.88 16 716 235U 32629 235U 538 (20% in U) -25 Puf -750 Puf -476 233U -14280 233U 1.65 16 151 235U (13% in U) -30 Puf 0 23% Denatured Dispersible Fuel 1.46 16 102 233u (12% in U) -32 P u ~ <strong>Energy</strong>-Center Constrained Fuel NU containing 16 338 235U 0.3% Pu -29 Puf Reference Fuel 1.91 16 105 235U (93% in U) -2 Puf 0 2331) 6500 235U 538 -900 Puf 0 2331) 4606 233U 0 -960 Puf 10699 235U 164 -870 Puf 5204 235U 548 -60 Puf 0 233u EA11 cases assume 75% capacity factor. For fresh fuel. :No credit. 250 kg minus 99 kg 235UIGWe-yr is equivalent to 63 ST minus 25 ST U,O,/GWe-yr; thus annual U308 requirement is 63 - 25=38 ST/GWe. :Excludes trans4 tion requirements and out-of-core inventories. 191 kg minus 86 kg 235U/GWe-yr is equivalent to 48 ST minus 21 ST U308/GWe-yr; thus annual U308 requirement is 48 - 21=27 ST/GWe. 'No credit for end-of-life core. 156 4688 114 3563 267 8281 38d 1 640e 0 0 73 2281 27f 1331e P W W
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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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- - I 4d _- t .- ! Lili L Ld id .-
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L .- k id .- I L: _ - I iclr .- i b
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I, G - -- I id ..- ! I _. I: L _.-
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huJ -- AI I ' b --- I bl --- t L L
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-- t Li - I' b -. c (u I i ai L i i
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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
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-
Page 77 and 78: t .. -. F 4d -- I ' L 0- 122, L _-
Page 79 and 80: L L; L t -I I ' b L -- t i b -- I;
Page 81 and 82: _- I -- L i d .-- L 4-1 1 Reference
Page 83 and 84: _- id L t I , 4d i, L id L 5 bi t h
Page 85 and 86: -- - . & I I ' h I ' Y 61 L -- I( L
Page 87 and 88: u -- x i I*i 1- bi 4-1 7 The use of
Page 89 and 90: la - i , I br -_ t c c L e L 4-1 9
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
Page 97 and 98: h 1' b t c i--; & I- & 1: i f 4-27
Page 99 and 100: c- i L L e I b 4-29 . safeguards fo
Page 101: L t i- bi L L t i 4-31 a significan
Page 105 and 106: F-- I iJ L ii - L c c 4-35 Referenc
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
Page 111 and 112: L I 1 I Ld I ie i-- 1 t' 4-41 4.4.2
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/
Page 117 and 118: L i; 1 I i; i 1. 2. 3. 4. 5. 6. 7.
Page 119 and 120: 4-49 Table 4.5-1. Fuel Utilization
Page 121 and 122: ments. 4-51 The calculations for LM
Page 123 and 124: 1. 2. 3. 4. 5. 6. 7. 8. 4-53 0 77-1
Page 125 and 126: Table 4.6-1. Comparison of Fuel Uti
Page 127 and 128: 4-57 _I 10 10' 2 2' CASE NUMBER -.
Page 129 and 130: 4-59 Most of the information availa
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Page 133: 4-63 on only the preliminary data p
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Page 138 and 139: ! 5-4 5.1. REACTOR RESEARCH AND DEV
Page 140 and 141: 5-6 As has been pointed out above,
Page 142 and 143: 5-8 the LMFBR on its reference cycl
Page 144 and 145: 5-10 The fuel performance program u
Page 146 and 147: . 5.1.2. Government Research and De
Page 148 and 149: 5-1 4 The first aspect of large pla
Page 150 and 151: 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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