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4-54 4.6. ALTERNATE FAST REACTORS 4.6.1. Advanced Oxide-Fueled LMFBRs T. J. Burns Oak Ridge National Laboratory One method of improving the breeding performance of the LMFBRs discussed in the previous section is to increase the core fertile loadings. Typically, this goal is accomplished by one of two means: redesign of the pins to accommodate larger pellet diameters or the use of a heterogeneous design (i.e., intermixed core and blanket assemblies). To maintain consistency with the "classical" designs considered in the previous section, using the same fuel elements for both concepts, the latter option was i pursued to assess the impact of possible redesign options. Table 4.6-1 summarizes some preliminary results from calculations for a heterogeneous reactor core model consisting of alternating concentric fissile and fertile annuli (primed cases) and compares them with results from calculations for corresponding homogeneous cores (unprimed cases). As the data in Table 4.6-1 indicate, the heterogeneous conffquration results in a significant increase in the overall breeding ratio relative to the corresponding homo- . geneous calculation. The heterogeneous reactors also require a much greater fissile loading for criticality due to the increase in the core fertile loading. However, the increase in the breeding gain more than compensates for the increased fissile requirements, resulting in an overall improvement in the fissile doubling time. On the other hand, because of the high fissile loading requirements, it appears that a heterogeneous model for the denatured cases with 12% enrichment (cases 6 or 7 of the previous section) is unfeasible; therefore, an enrichment of 120% was considered as the minimum for the denatured heterogeneous configuration. While the denatured heterogeneous configurations result in an increase in the overall breeding ratio, it is significant that the 233U component of the breedinq ratio also improves. Figure 4.6-1 depicts the breeding ratio components for both the homogeneous and heterogeneous denatured configurations. as the upper limit.) As Fig. 4.6-1 indicates, the heterogeneous confiaurations are clearly superior from the standpoint of 233U self-sufficiency (i.e. , requirinq less makeup requirements). Moreover, if enrichments in the range of 304: - 40% are allowed, it appears possible for a denatured heterogeneous reactor to produce enough 233U to satisfy its own equilibrium cycle fuel requirements. Production reactors would therefore be required only to supply the initial inventory plus the additional makeup consumed before the equilibrium cycle is reached. (Aaain , the 233U/Th LMFBR is included
Table 4.6-1. Comparison of Fuel Utilization Characteristics and Performance Parameters for Homogeneous and Heterogeneous LMFBRs Under Various Oxide-Fuel Options Equilibrium Cycle Reactor Materials Fissile Initial Breeding Doubling Fissile Fissile Fissile Dlscharge Axial Internal Radial Ratio, Time (yr) Inventory Charge (kg/GWe-yr) Case' Driver B1 anket Blanket B1 an ket MOEC (RF.0.98) (kg/GWe) (kg/GWe-yr) 23 3u PUT 1 PU/U U 1' PU/U U 2 PU/U U 2' PU/U U 4 Pu/Th Th 4' Pu/Th Th 8b 33U/ (U+Th) Th 8' 233u/u U 9= 3U/ (U+Th ) Th 9 I' 23 3u/u U 10 3U/Th Th 10' %/Th Th - ~ Energy-Center-Constrained Fuels U 1.27 12.7 U 1.50 10.2 Th 1.27 13.1 Th 1.44 12.9 Th 1.14 36.1 Th 1.35 18.2 Dispersible Denatured Fuels Th 1.09 43.0 Th 1.29 18.0 Th 1.05 112.3 Th 1.29 20.8 Reference Fuels e Th 1.02 - Th 1.20 30.1 2270 804 3450 1173 2291 804 3725 1250 2712 920 41 59 1365 2208 834 3338 1624 2322 875 4062 1354 241 9 91 1 371 8 1309 '%apacitv factor is 75%; unprimed cases are for homoseneous cores, primed cases for heterogeneous cores; .. see Tabie 4.5-1 for case description. b20% *33u/u. =40% 233U/U; 'Included for illustrative purposes only; exceeds design constraints. =Reference fuels are considered only as limiting cases. - 154 536 583 800 698 1548 835 1457 926 1454 991 1517 834 1013 427 808 P 203 306 78 108 0 0 VI v1
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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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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
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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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Page 87 and 88: u -- x i I*i 1- bi 4-1 7 The use of
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Page 95 and 96: 4-25 Initial analyses of spectral-s
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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
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Page 144 and 145: 5-10 The fuel performance program u
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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Page 164 and 165: 6-4 persed areas ensured - a fact w
Page 166 and 167: 6-6 6.1.2. Reactor Options The reac
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Page 172 and 173: 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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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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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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..a 4 I- 1 ' u c1 Y u L 7-39 betwee
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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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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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