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4-28 3. Refueling System Modifications - A t the end of each operating cycle, spent fuel must be discharged and fresh fuel inserted into the reactor (typically 1/3-of the core loading is replaced each year), and the light water present at end of cycle must be replaced with a D20-H20 mixture before the reactor can be returned to power operation. Refueling procedures and equipment must be developed which will allow these operations to be performed with minimum D20 inventory requirements. Minimizing the D20 inventory is important to the economics and commercial feasibility of the SSCR, since the cost of D20 represents roughly 75% o f the additional capital expenditures required to realize spectral- shift control. times because of the adverse effect on capacity factor and the resulting increase in power cost. Care must also be taken to ensure that refueling does not increase outage The exposure of personnel to tritium qenerated in the coolant must also be mini- mized during refueling operations. 4. D20 Upgrader Design - Although D20 upgraders have yet to be employed in con- junction with spectral-shift control , similar units have operated on CANDU reactors, and vacuum distillation columns are also utilized in heavy-water production facilities. Thus, the technical feasibility of the D20 upgrader can be considered as demonstrated. However, a conceptual upgrader design optimized for the specific demands of the SSCR must be developed so that its cost can be determined. The upgrader is probably the single most significant and costly piece of equipment which must be added to realize spectral-shift control. 5. Licensability and Safety - Although the spectral-shift-controlled reactor is not expected to raise any new safety, licensing or environmental issues except the basic issue of tritium production and containment, a number of core physics parameters are changed sufficiently that the response to postulated accidents must be evaluated. most significant of these appears to be the somewhat different moderator temperature co- efficient of reactivity, which could lead to a number of potentially more severe accidents early in cycle when the D20 concentration is relatively high. The D20 dilution accident must also be addressed; this accident is analogous to the boron dilution accident in the poison-controlled PWR, but the response to D,O dilution may be more rapid and hence the accident may be potentially more severe than its counterpart in the PWR. Finally, it should be pointed out that while the relationship of the SSCR to the I LWR gives it market advantages, it also gives it some disadvantages relative to other alternatives. Although the SSCR demand for U308 will be less than that of the conventional LWR, the basic properties of light water and the LWR design characteristics inherent in the SSCR will limit its fuel utilization efficiency to lower levels than those achievable with other alternatives such as the HWR. On the other hand, the prospect for early and widespread deployment may mean that it could effect a more significant reduction in over- all system U308 demand than might be achievable with other alternatives, even though the inherent resource utilization of an individual SSCR plant may be less than that of other systems. Employing denatured SSCRs would allow additional time to develop effective The
c- i L L e I b 4-29 . safeguards for breeder reactors which will eventually be required. These breeders might produce 233U, which, as pointed out above, could then be denatured and used in SSCRs. 1. 2. 3. 4. 5. 6. References for Section 4.2 T. C. Engelder, et al., "Spectral Shift Control Reactor Basic Physics Program, BAW- 1253 (November 1963). M. C. Edlund, "Developments in Spectral Shift Reactors," Proceedings of the Third International Conference on the Peaceful Uses of Atomic Energy," Vol. 6, p. 314-320, Geneva, Switzerland (1964). J. Storrer, "Experience with the Construction and Operation of the BR3Dulcain Experiment," Symposium on Heavy Water Power Reactors, IAEA Vienna (September 11-15, 1967). J. Storrer, et al., "Belgonucleaire and Siemens PWRs for Small and Medium Power Reactors," Proceedin s of a Symposium on Small and Medium Power Reactors, IAEA Oslo (October 12-16, 1970f. Letter, R. A. Matzie (Combustion Engineering) to J. C. Cleveland (ORNL), "Mass Balances for SSCRs and LWRs," (May 10, 1977). Nonproliferation Alternative Systems Assessment Program - Preliminary Plan (draft) May 1977.
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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.
Page 48 and 49: 3.18 There are three approaches whi
Page 50 and 51: 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
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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
Page 97: h 1' b t c i--; & I- & 1: i f 4-27
Page 101 and 102: L t i- bi L L t i 4-31 a significan
Page 103 and 104: ~ kc'l c" -1 r-"! r! r-'i c Table 4
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
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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 -.
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
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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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