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GRlBRLL 1 U-239 4-46 As can be seen, the 239Pu content peaks at '~r 30 MWD/kg,decreasing thereafter. The higher Pu isotopes tend to peak at higher U-240 U-242 burnups so that at discharge 242Pu doniio.olG%, , nates. Compared to an LLJR with LEU ftlel, 50 ,oo nwOlac the PBR v:ith HEU/Th fuel discharges only 8% HI)(II.TLUC"I.l.RuE1rEW.rT. as much fissile plutonium. Furthermore, the Fig- 4-4-10 Buildup of the Plutoniur fissile fraction of the discharged plutonium Isotopic Composition in the MEU/Th Fuel. is only 39% compared to 71% for an LWR. Table 4.4-8 presents U308 requirements of the various once-through cycle^.^,^ The 30-yr cumulative U308 demands for the MEU/Th once-through cycle and the HEU/Th once- through cycle were determined by explicit 30-yr calculations.8 The 30-yr cumulative U308 demands for the LEU, the seed-and-breed MEU/Th and the seed-and-breed HEU/Th cycles were determined from the U308 demand for the equilibrium cycles and estimates of the inventory of the startup core and of the requirements for the approach to equilibrium.8 As can be seen from Table 4.4-8, from the viewpoint of U308 utilization for oncethrough cycles in the PBR, LEU fuel is the least favorable and HEU/Th fuel is the most favorable with MEU/Th fuel having a U308 utilization between HEU/Th and LEU fuel. It should be noted that the cases presented in Table 4.4-8 do not include recycle of the bred fissile material. Under these no-recycle constraints the MEU/Th cases have a 30-yr U3O8 demand comparable to a PWR operating with uranium and self-generated Pu recycle (see Case F, Table 4.1-3). Thus if recycle were performed with the MEU/Th PBR cases, significantly less U308 would be required than for the PWR with U and Pu recycle. One option for the recycle in the seed-and-breed MEU/Th PBR case would be to cycle the fertile balls back into the feed stream (without reprocessing) for an additional pass through the pebble bed if the irradiation behavior of the fertile balls permits. Table 4.4-8. U308 Requirements for Once-Through PBR Cyclesa ~- Case 1, Case 2, Case 3, Case 4, Case 5, Seed and Ereed Seed and Greed LEU 11 E U / T h MEU/Th HEU/Th HEU/Th Eauilihriun cycle 143 135 137 126 126 U308 demand, ST/GWE-yr 30-year cumulative U308 demand,b ST/GWE 45OOc 41 84d 4200' 4007d 40OOc 'The basis for these requirements is a lOCO-H'.le plant operating at 752 capacity factor for 30 years; tails composition is assumed to be 0.2 w/o. 'Assures no recycle. c Estimated value; could differ from an explicit 30-yr calculation by 5 3%. dExplicit 30-yr calculation. L L
L i; 1 I i; i 1. 2. 3. 4. 5. 6. 7. 8. 4-47 References for Section 4.4 Reactor Design Characteristics and Fuel Inventory Data, compiled by HEDL, September 1977. Thorium Aseessment Study Quarterly Progress Report for Second Quarter Fiscal 1977, ORNL/TM-5949, Oak Ridge National Laboratory (June 1977). Letter, A. J. Neylan, Manager, HTGR Generic Technology Program, to K. 0. Laughon, Jr., Chief, Thermal Gas-Cooled Reactor Branch, DOE/NRA, "Technical Data Package for NASAP," March 3, 1978. M. H. tierrill and R. K. Lane, "Medium Enriched Uranium/Thorium Fuel Cycle Paramtric Studies for the HTGR," General Atomic Report GA-A14659 (Deceniber 1977). Letter, R. F. Turner, Manager, Fuel Cycles and Systems Department, General Atomic Company, to T. Collins, DOE/NPD, May 8, 1978. Thorium Assessment Study Quarterly Progress Report for Third Quarter Fiscal 1977, ORNL/TM-6025, Oak Ridge National Laboratory. E. Teuchert, et al., "Once-Through Cycles in the Pebble-Bed HTR," Trans. Am. Nucl. SOC., 27, 460 (1977). December 197n. (Also published as a KFA-Julich report Jul-1470, Letter, E. Teuchert (Institut Fir Reaktorenturcklung, Der Kernforschungsanlage Julich GmbH) to J. C. Cleveland (ORNL), "Once-Through Cycles in the Pebble- Bed HTR," May 19, 1978.
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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
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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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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 105 and 106: F-- I iJ L ii - L c c 4-35 Referenc
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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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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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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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