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5-8 the LMFBR on its reference cycle are currently being revised, and a study of L.e denatured fast breeder fuel cycle, which includes fast transmuters and denatured breeders, is included as part of the INFCE program (International Nuclear Fuel Cycle Evaluation). from the INFCE study should be available in the near future. 5.1.1. Light-Water Reactors The results Preliminary evaluations of design and safety-related considerations for LWRs operating on the conventional thorium cycle indicate thorium-based fuels can be employed in LWRs with little or no modification. Consequently, the R&D costs given here have been estimated under the assumption that denatured fuel will be employed in LWRs of essentially present design. This assumption is not meant to exclude minor changes to reactor design (for example, changes in the number of control drives, shim loadings, or fuel management, etc.) but rather reflects our current belief that design changes necessitated by DUTH fuels will be sufficiently straightforward so as to be accommodated within the engineering design typically performed for new plants. As has been described in the discussion above, the first phase of such fuel-cyclerelated research consists of the development of a data base from which safety-related parameters and fuel performance can be predicted in subsequent core physics design and safety analysis programs. First, existing thorium materials and fuel performance information should be thoroughly reviewed, and a preliminary evaluation of safety and licensing issues should be made in order to identify missing information and guide the subsequent development program. Although this initial phase is required to fully define the required data base R&D, it is possible to anticipate in advance the need to establish information in the areas of physics verification and safety-related fuel performance. As shown in Table 5.1-1, the physics verification program under data base development is estimated to cost %$lo million. This program should be designed both to provide the information required to predict important safety-related physics parameters and to demonstrate the accuracy of such predictions as part of the safety analysis. Improved values must be obtained for cross sections of thorium and of isotopes in the thorium depletion chains, such as 233U and protactinium, all of which have been largely neglected in the past. Resonance integral measurements should also be performed for denatured fuels both at room temperature and at elevated temperatures, such experiments being very important for accurately calculating safety-related physics characteristics and also for establishing the quanti ties of plutonium produced during irradiation. Finally, an LWR physics verification program should include a series of critical experiments, preferably both at room temperature and at elevated moderator temperatures, for each of the fuel types under consideration (i .e. , for thorium-based fuels utilizing denatured 23sU, denatured 233U, or plutonium). These experiments would serve as a basis for demonstrating the adequacy of the cross-section data sets and of the ability of analytical models to predict such safety-related parameters as reactivity, power distributions, moderator temperature reactivity coefficients, boron worth, and control rod worth.
5-9 Table 5.1-1. Government Research and Development Required to Convert Light-Water Reactors to Denatured Uranium-Thorium Fuel Cycles (20% 235U/238U-Th or 20% 233U/238U-Th) Assumptions: All basic reactor R&D required for commercialization of LWRs operating on their reference fuel cycle (LEU) has been completed. Use of denatured fuel can be demonstrated in a current-generation LWR. Because utility sponsoring demonstration will be taking some risk of decreased reactor avilability, a 25% government subsidy is assumed for a 3-year demonstration program. Note: LWRs can be operated on the denatured 235U/238U-Th fuel cycle before any other reactor system; however, they cannot be economically competitive with LWRs operating on the LEU once-through cycle because higher U308 requirements are associated with thorium fuel. Any commercial LWRs operating on a denatured cycle before the year 2000 must be subsidized. A. Data base development Research and Development Al. Physics verification program 10 Improve cross sections for Th, 233U, Pa, etc. Measure resonance integrals for denatured uranium- thorium fuels at room temperature and at elevated temperatures. Perform and analyze critical experiments for each fuel. A2. Fuel-performance program Perform in-reactor properties experiments Perform power ramp experiments Perform fuel-rod irradiation experiments Perform transient tests cost ($MI I (30 - 150)= B. Reactor components development (develop hand1 ing 5 - 25 equipment/procedures for radioactive 232Lcon- taining fresh fuel elements). C. Demonstration design and licensing 20 - 100 C1. Develop core design changes as required for denatured fuels C2. Perform safety analysis of modified core D. C3. Prepare safety analysis report (SAR); carry through licensing Demonstration of LWR operating on denatured fuel 5ob - 200- ( pro ba b 1 y 5U / 8U -T h ) aWould be included in fuel recycle R&D costs (see Section 5.2). %Jotential government subsidy; i.e., total cost of demonstration is $200M.
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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 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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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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Y m I I I . aro ID0 10.00 4-5 ORNL-
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Page 164 and 165: 6-4 persed areas ensured - a fact w
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Page 172 and 173: Table 6.1-4. Nuclear Policy Options
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Page 184 and 185: 6-24 The potential nuclear contribu
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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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..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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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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