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4-42 Table 4.4-3. PBR Fuel Element Design outer radial core zones. The enrichment Ball diameter 6 cm Thickness of graphite she1 1 0.5 cm Graphite density 1.70 g/cm3 of the inner zone is 7.9 at.% and that of the outer zone is 11.1 at.%. Case 2, MEU/Th. (U + Th)02 fuel with 201 enriched uranium i s Toaded into the coated fuel particles. The heavy metal loading in the MEU/Th fuel element is between that of the THTR and AVR elements. Case 1, the radial power is flattened by the choice of fissile loading of the elements in the inner and outer radial core zones, 6.85 and 11.4% respectively. The coated particles would require some development and testing. As in Case 3, Seed and Breed MEU/Th. (U + Th)O, fuel with 2oI enriched uranium is loaded By thus separating the seed and into seed elements and Tho, is loaded into breed elements. breed elements, 236U bred into the seed elements will not have contaminated the 233U produced in the breed elements in case recycle is opted for later. Graphite balls are added to the inner core zone to adjust the carbon/heavy metal ratio (C/HM) to that of the outer zone. The heavy metal loading of 6 g HM/ball in the seed elements is essentially the same as in the AVR. The feasibility of a considerably heavier loading of the breed elements, 16.54 g HM/ball, is currently being tested. Case 4, HEU/Th. (U + Th)O, fuel with 93% enriched uranium is loaded into the coated fuel particles. The coated particle and fuel element designs are essentially identical to those of THTR fuel elements, which have been licensed and are being manufactured. modification is the fissile loading. The only Again the fissile loading of the elements in the inner and outer radial core zones is varied to flatten the radial power distribution, the inner zone fissile loading being 6.23% of the heavy metal and the outer zone fissile loading being 10.9%. Case 5, Seed and Breed HEU/Th. (U + Th)02 fuel with 93% enriched uranium is loaded into seed elements and breed elements contain Tho, only. tened by the choice of the mixing fraction of seed and breed balls in the inner and outer radial core zones, and graphite balls are added to the inner zone to adapt the C/HM ratio to that of the outer zone. In the seed elements the HEU is mixed with some Tho, in order to achieve a prompt negative Doppler coefficient. Again the heavy metal loading of the balas is essentially the same as that in the AVR and the feasibility of the loading of the breed elements is being tested. The radial power profile is flat- The mass flow data for the equilibrium cycle of each of the five cases are pre- sented in Table 4.4-7. The high thermal cross sections of 239Pu, ,‘+OPu and 241Pu, the soft spectrum, and the low self-shielding of the fuel element design lead to a very high in-situ utilization of the fissile plutonium (95% for the MEU/Th cycles). In addition, the high burnup results in the low discharge plutonium fissile fractions shown in Table 4.4-7. The buildup of plutonium isotopes in the MEU/Th cycle is shown in Fig. 4.4-1. L c
4-43 Table 4.4-4. PBR Coated Particle Design i, Kernel Carbon Coatings L t i :- i -. . L L L L L i Type Materi a1 Diameter Density Thicknesses Densities ( gIcfi13 1 (lJm) ( g/cm3 1 I U/Th02 400 9.50 85/30/80 1.0/1.6/1.85 I1 U/Th02 400 9.50 50180 1.011.85 I11 UOZ 800 9.50 11 0180 1.011.85 Table 4.4-5. Composition of PBR Fuel Elements Heavy Metal Moderati on Identi f i cati an Type of Loading Ratio Coated Particlea (glball) ('iC/"Hff) N 1 I 11.24 325 t?Z I 8.G7 458 s1 I1 €.O 61 7 52 I1 6.0 629 til I1 20.13 180 82 I1 16.54 220 L1 I11 9.88 380 L2 I11 11.70 320 G a See Table 4.4-4. Carbon Table 4.4-6. Composition of PBR Core Regions Used in Mass Flow Calculations Inner Core Outer Core Case Fuel Element Type' Fissile hading Fuel Element T~~~ Fissile Loading (Fractional Mixing) ("fis/"HM) (Fractional Mixing) ( Nf i sINHM) 1, LEU 11 (1.0) 2, MEU/Th 3, Seed and Breed MEU/Th 1.12 (1.0) S2 0.485 B2 t 0.305 G (0.210) 4, HEU/Th M1 (1.0) 5, Seed and S1 (0.40) Breed HEU/Th B1 (0.39) G (0.21) U See Table 4.4-5. 0.079 L2 (1.0) 0.111 0.0685 M2 (1.0) 0.114 0.20 S2 (0.765) 82 (0.235) 0.20 0.0623 M1 (1.0) 0.109 0.27 S1 (0.69) B1 (0.31) 0.27
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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
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 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
Page 109 and 110: Table 4.4-1. Fuel Utilization Chara
Page 111: L I 1 I Ld I ie i-- 1 t' 4-41 4.4.2
Page 115 and 116: HEU/Th 0.59 Seed i3 Breed 0.58 HEU/
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Page 119 and 120: 4-49 Table 4.5-1. Fuel Utilization
Page 121 and 122: ments. 4-51 The calculations for LM
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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 -.
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Page 138 and 139: ! 5-4 5.1. REACTOR RESEARCH AND DEV
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Page 144 and 145: 5-10 The fuel performance program u
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Page 148 and 149: 5-1 4 The first aspect of large pla
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Page 152 and 153: I DATA BASE DEMu)pMENT DEMO DESIGN
Page 154 and 155: j ~ 5-20 The R,D&D costs are highes
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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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