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These studies could 0 Thorium fuel 7-50 provide guidance for the following R&D programs: cycle R&D to investigate the use of MEU(235)/Th, MEU( 233)/Th (denatured 233U), and Pu/Th fuels in LWRs and HWRs (the latter in cooperation kith Canada). 0 Studies to consider denatured 233U or 235U fuels as candidates for the HTGR reference fuel cycle. This program might also include the LWBR fuel cycle. 0 Thorium technology studies, particularly for blanket assemblies, as an integral part of the FBR programs (LMFBRs and GCFBRs). 0 Exploratory work with utilities and PWR and BWR vendors for qualification and use of MEU/Th and Th fuel rods in commercial reactors. An example of the beneficial use of Th would be in corner rods of the BWR fuel assembly. L c
t a APPENDICES
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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
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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
Page 210 and 211: 6-50 (4) If all plutonium produced
Page 213 and 214: I d r-- 1 > w I r- k z r L id r- .
Page 215 and 216: L 1 L u without benefit of U.S. exp
Page 217 and 218: L a, - L i -- k; L t IJ L 7-7 While
Page 219 and 220: 7-9 Viewed solely from the plutoniu
Page 221 and 222: L L i; i; 7-1 1 routinely in LWRs a
Page 223 and 224: 'I 7-1 3 t I: k: The isotopic compo
Page 225 and 226: U L L L L ld 1 i" * required 233U m
Page 227 and 228: I I, i 7-1 7 ii I 1 I L L k L i Thr
Page 229 and 230: li i i L Li L & I ' i kr ii L i h i
Page 231 and 232: 7-21 7.3. PROSPECTS FOR IMPLEMENTAT
Page 233 and 234: L I L t L i L i 1 L 7-23 7.3.1. Pos
Page 235 and 236: 7-25 7.3.2. Considerations in Comme
Page 237 and 238: .. I b k; L; i b b 1J I L 7-27 cycl
Page 239 and 240: 7-29 7.4. ADEQUACY OF NUCLEAR POWER
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Page 243 and 244: x ibd 1 .. I i, L -- i t Table 7.4-
Page 245 and 246: 7-35 cycled in Pu/Th converters, th
Page 247 and 248: L 1' b I_- ,- i b -- I ' b L 7-37 T
Page 249 and 250: ..a 4 I- 1 ' u c1 Y u L 7-39 betwee
Page 251 and 252: L e, I I ' lb t 7-41 Systems that u
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Page 255 and 256: 7-45 j I Table 7.5-1. Integrated As
Page 257 and 258: - isi. c ‘Id i L c 7-47 Although
Page 259: e Other e e e On the e 7-49 technol
Page 263 and 264: A-3 Appendix A. ISOTOPE SEPARATION
Page 265 and 266: I] 1- $i ill 8 LI b' The Gas Centri
Page 267 and 268: id A- 7 The Component Preparation L
Page 269 and 270: i ?L 1- U t L fl bi L c u La -- ti
Page 271 and 272: p; ‘U i-- L ,c c Japan A-1 1 Tabl
Page 273 and 274: 13 A-13 L" efficient of the units d
Page 275 and 276: L L L t I h h u L; _- t f is throug
Page 277 and 278: u A-1 Aerodynamic Methods 7 Both th
Page 279 and 280: i i d .- I . ii hi L i: i t ' Li 1
Page 281 and 282: la t L I I, lj ir 1 Li c I L L' B-1
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
Page 287 and 288: LJ L L1 a .E 4' P Y W 5 18 2 16 : 0
Page 289 and 290: Appendix C. DETAILED RESULTS FROM E
Page 291 and 292: 1 i; Li b L lkd t L L I hd I ' L; i
Page 293 and 294: L c-5 The introduction of the class
Page 295 and 296: i ' ibd 1 b i L L i L I Li . . b b
Page 297 and 298: E , 1 ' b _. I ' L 1 b _- i G i' b
Page 299 and 300: -, ii I ; b i- ii L b 4 i L L i‘
Page 301 and 302: _- I ii I _ _ I L I td C i b L i, L
Page 303 and 304: Qulatiw klur W i t y hilt (*I thrmg
Page 305 and 306: L c c b - i ii L r D-1 Appendix D.
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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[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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