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4-14 Case G allows one possible means for utilizing the plutonium bred in the dispersed reactors. Plutonium discharged from LEU-LWRs is used to provide the initial core fissile requirements as well as the fissile makeup requirements. This plutonium is blended in a U02 diluent consisting of natural or depleted uranium. The plutonium discharged from the UO,/PuO, reactor is continually recycled - with two years for reprocessing and refabrication - through the reactor. In the equilibrium condition, plutonium discharged from about 2.7 LEU-fueled LWRs can provide the makeup fissile Pu requirement for one U02/Pu02 LUR. In Case H the Pu02/Th02 LWR also utilizes plutonium discharged from LEU-LWRs to provide the initial core fissile requirements and the fissile makeup requirements. This plutonium is blended in a Tho, diluent. The isotopically degraded plutonium recovered from the PuO2/ThO2 LWR is blended with LEU-LWR discharge plutonium (of a higher fissile content) and recycled back into the Pu02/Th02 LWR. Not only does this case provide a means of eliminating the Pu bred in the dispersed reactors but, in addition, also provides for the production of 233U that can be denatured and used to fuel dispersed reactors. ! The Pu02/Th02 LWR of Case I is similar to that in Case H in that plutonium discharged from LEU-LWRs is used to provide the fissile requirements. However, the isotopically degraded plutonium recovered from the PuO,/ThO, LWR is not recycled into an LWR but is stored for later use in a breeder reactor. Case J involves the use of highly enriched uranium blended with Tho2 to the desired fuel enrichment. The uranium enrichment in HEU fuels was selected as 93.15 w/o on the basis of information in Ref. 7. Initially all fuel consists of fresh HEU/Th fuel assemblies. Once equilibrium recycle conditions are achieved, about 35% of the fuel consists of this fresh makeup fuel, the remaining fuel assemblies in each reload batch containing the recycled (but not re-enriched) uranium oxide blended with fresh Tho2. Table 4.1-1 provides a summary, obtained from the detailed mass balance information, of initial loading, equilibrium cycle loading, equilibrium cycle discharge, and 30-year cumulative U308 and separative work requirements. All recycle cases involve a two-year ex-reactor delay for reprocessing and refabrication. It is important to point out that for cases which involve recycle of recovered fissile material back into the same LWR, in "equi 1 ibrium" conditions the makeup requirement for a given recycle generation is greater than the difference between the charge and discharge quantities for the previous recycle generation because of the degradation of the isotopics. This is especially important in Case H where, for example, the fissile content of the plutonium drops from about 71% to about 47% over an equilibrium cycle. Comparing Cases A and B of Table 4.1-1 indicates the penalties associated with implementation of the MEU/Th cycle relative to the LEU cycle under the restriction of no recycle. The MEU/Th case requires 40% more U308 and 214% more separative work than the LEU c I: h:
-- - . & I I ' h I ' Y 61 L -- I( L L 4-15 case, Clearly the MEU/Th cycle would be prohibitive for "throwaway" options. A second significant result from Table 4.1-1 is given by the comparison of Case D, MEU/Th with uranium recycle and Case F, LEU with uranium and self-generated plutonium recycle, The U308 demand in each case is the same, although the MEU/Th cycle requires increased separative work. Additionally it should be noted that in Case D the MEU/Th fuel also produces significant quantities of plutonium, an additional fissile material stockpile which is not recycled in this case. Table 4.1-1. Fuel Utilization Characteristics for PWRs Under Various Fuel Cycle Optionsenb Separative Work Initial Equilibrium Cycle U 0 Requirement Requirement Fissile Fissile Fissile '(ST/GU;!- j103 kg SWU/GWe) Inventory Charge Discharge Conversion Burnup 30-yr e Case Fuel Type (kq/GWe) (kalGWe-vrl (ka/GWe-vr) Ratio (MWD/kq HM) Initial' Tot%dInitial e Total A B C D E F G H I J LEU. no recycle 1693 235U MEU/Th. no recycle 2538 235U LEU, U recycle 1693 235U MEU/Th, self- 2538 2sU generated U recycle Denatured 33U02/Th02. 1841 233U U recycle (exogenous 27 235U 33U makeup) LEU. recycle of U + self-generated Pu 1693 2sU PuOp/UO2. Pu recycle 1568 Puf 546 235U PuOZ/ThOz. Pu recycle 2407 Puf Pu02/Th02. single Pu 2407 Puf pass HEWTh. self-generated 2375 235U U recycle Dispersible Resource-Based Fuels 794 235u 215 23511 174 Puf 0.60 30.4 1079 235U 260 23% 0.63 32.6 384 23% 71 Puf - 0.60 30.4 313 233U8 675 235U8 282 23S8 0.66 257 235U8 95 Puf0 32.6 Dispersible Denatured Fuel 750 233U 446 233U 33.4 29 235U 43 235U 63 Puf Energy-Center-Constrained Fuels 612 235U 193 235U 0.61 30.4 258 Puf 288 Puf 1153 Puf 858 Puf 0.63 30.4 173 235U 108 235U 1385 Puf 696 Puf 33.0 272 233U 1140 Puf 410 Puf 33.0 284 23% Reference Fuel 388 23% 377 233U 0.67 33.4 504 235U 172 23511 392 5989f 638 8360 392 4946 638 4090 392 4089 100 1053 597 3453 :All cases assume 0.2 w/o tails and 75% capacity factor. %11 calculations were perfoned for the mwt, 13WMWe tombustion Engineering System BOm reactor design. ssumes 1.0% fabrication loss and 0.5% conversion loss. 4 o credit taken for end of reactor life fissile inventory. ssumes 1.0% fabrication loss. 9 203 3555 580 7595 203 3452 580 3632 233 2690 0 0 596 3436 An additional case is considered I n Chapter 6 in which an extended exposure (43 MWO/kg HM) LEU-PUR on a once-through cycle results in a 6% reduction in the 30-yr total U 08 requirements, while still requiring essentially the same enrichment (SUU) requirements. Scinewhat less plutonium is disciarged from the reactor because of a reduced conversion ratio. Values provided are representatlve of years 19-23. 'Reference fuels are considered only as limiting cases. Differences in the nuclide concentrations of fertile isotopes from case to case result In differences in the resonance integrals of each fertile isotope due to self-shielding effects, thus significantly affecting the conversion of fertile material to fissile material. Table 4.1-2 gives the resonance integrals at core operating temperatures for various fuel combina- tions. Although the value of the 238U resonance integral for an infinitely dilute medium is much larger than the corresponding value for 232Th, the resonance integral for *38U in LEU fuel is only 25% larger than that for 232Th in HEU/Th fuel, indicating the much larger amount of self-shielding occurring for 238U in LEU fuel. These two cases represent extreme values,
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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
Page 34 and 35: 232" Fig. 3.0-1. Decay of 232U. ORN
Page 36 and 37: 3-6 3.1. ESTIMATED U CONCENTRATIONS
Page 38 and 39: 3-8 The values in Table 3.1-2 are a
Page 40 and 41: 3-1 0 3.2. RADIOLOGICAL HAZARDS OF
Page 42 and 43: 3-1 2 232u IN RECYCLED HTGR FUEL (p
Page 44 and 45: 3-14 3.2.2 Toxicity of 232Th Given
Page 46 and 47: 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
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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
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Page 87 and 88: u -- x i I*i 1- bi 4-1 7 The use of
Page 89 and 90: la - i , I br -_ t c c L e L 4-1 9
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 and 98: h 1' b t c i--; & I- & 1: i f 4-27
Page 99 and 100: c- i L L e I b 4-29 . safeguards fo
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
Page 123 and 124: 1. 2. 3. 4. 5. 6. 7. 8. 4-53 0 77-1
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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c e E c
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! 5-4 5.1. REACTOR RESEARCH AND DEV
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5-6 As has been pointed out above,
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5-8 the LMFBR on its reference cycl
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5-10 The fuel performance program u
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. 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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