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! 3-28 Table 3.3-3. Enriched Proauct Compositions (Weight Fraction in Uranium) Isotope Fuel Type B Feed Product Fuel Type c Feed Product 2321) 5.02 x lom4 4.1545 x 10-3 6.565 x loe4 5.626 x 233u 0.11861 1 0.90 0.11498 0.90 2341) 0.008523 0.03757 0.0351 08 0.0901 2351) 0.00231 7 0.00376 0.01255 0.00379 23611 3.6 10-5 1.98 10-5 0.005327 1.73 10-4 2381) 0.87001 1 0.05450 0.831 228 3.124 x lo-'+ 2s3U in Tails 0.01 0.01 Feed Flow, 832 kg U/yr Product F1 ow, 100 kg U/yr When removed from the plant, the UF, product would be condensed and probably stored in monel cylinders. gamma dose rates that could be expected from the unshielded cylinders are as shown in Table 3.3-5. To reduce these product dose rates to acceptable levels would require substan- tial shielding. As an example, Table 3.3-6 shows the shielding required to reduce the dose rate at 1 ft to 1.0 and 50 mr/hr. If it is assumed that the cylinders were sized to hold 16 kg of UF6, the 859 Table 3.3-4. Gamma Radiation Level in an Enrichment Plant as a Function of 232U Concentration Tjzu Concentration Radiation Level (r/hr) (wt X ) at Equi 'I i bri urn* 2.0 6.8 1 .o 3.4 0.5 1.7 0.1 .34 100 0.001 .0034 0.0001 .00034 * Within an infinite array of centrifuges. bi
krd i 1 t - 3-.29 Table 3.3-5. 232U-Induced Gamna-Ray Dose Rates from Unshlelded Monel Cylinders Containing 16 kg of UF, Dose Rate (r/hr) Distance from Decay Time* Cy1 inder (days) 0.1 wt % 232U 0.6 wt % 2320 Contact 10 40.2 242 1 Foot 1 Meter 30 90 Equi 1 . 10 30 90 Equi 1. 10 30 90 Equi 1. 194 654 7,046 4.2 20.4 68.6 740 0.85 4.1 13.8 149 *Time measured from chemical separation from thorium. 1,166 3,922 42,300 Table 3.3-6. Shielding Required to Reduce 232U-Induced Gamna-Ray Dose Rates from Monel Cylinders Containing 16 kg of UF6* 25.4 122 41 2 4,440 5.1 24.6 82.9 894 Concrete Thickness Icm) .. Design Dose Rate Decay Time** (mr/hr) (days) D.1 wt % LSZU 0.6 wt % 2~ U 1 .o 50 *Distance from source to shield = 1 ft. 30 101 90 114 Equil . 138 30 62 120 132 157 90 74 92 Equi 1 . 98 116 **Time measured from chemical separation from thorium. 80
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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
Page 7 and 8: 1, L L t i Ltr 1 L L V PREFACE AND
Page 9 and 10: L i Li 1, I b k b id ii t L id b i
Page 11 and 12: I L bi i; L 7.3.1. Possible Procedu
Page 13 and 14: i xi I b L ABSTRACT A fuel cycle th
Page 15 and 16: I b .- i, hd t t CHAPTER 1 INTRODUC
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Page 27 and 28: L - i' u i Lt L r- L t- b L 2-7 den
Page 29 and 30: 2-9 1. Nuclear power is limited to
Page 31: e Isr i L i- b t CHAPTER 3 ISOTOPIC
Page 34 and 35: 232" Fig. 3.0-1. Decay of 232U. ORN
Page 36 and 37: 3-6 3.1. ESTIMATED U CONCENTRATIONS
Page 38 and 39: 3-8 The values in Table 3.1-2 are a
Page 40 and 41: 3-1 0 3.2. RADIOLOGICAL HAZARDS OF
Page 42 and 43: 3-1 2 232u IN RECYCLED HTGR FUEL (p
Page 44 and 45: 3-14 3.2.2 Toxicity of 232Th Given
Page 46 and 47: 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11.
Page 48 and 49: 3.18 There are three approaches whi
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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 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
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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 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
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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
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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
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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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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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