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28 Table 14. Effect of nuclide density on key resonance cross sections 232Th 2288 2.6% 0.5742 2408 2.52 0.6048 2582 2.44 0.6300 2 800 2.37 0.6636 3318 2.21 8.7332 238U 350 9.03 8.31160 48% 7.86 0.3781 658 6.85 0.4452 722 6.32 0.4563 800 6.22 0.4976 47.2 56,O 8.62 15.8 25.9 40.8 16.4 26*3 33.3 32. a 19 17 39.9 45.6 83 64 27. 5 27.3 58 56 22.9 21.6 68 48 Spectral. effects are also important, because a more thermal spectrum improves the neutron yield of both 233U and 235U but also results in more parasitic capture in these fissile nuclides. To illustrate thPs, Table 16 shows the effective neut~~i~ yield for the hard spectrum of core A vs the soft spectrum of core B. while uaf/oa within each ner~trsn group shows relatively little change, the overall ratio shows a 3% increase in yield because of the softer spectrum.
29 Table 16. Effect of neutron spectrum OR neutron yield for homogenized cell material A Resonance 6.338 A The rma 1 1 * 442 w Overall 1.050 B Re smanc e 8.330 B Thermal 1 e 432 B Overall 1 e 880 a See Fig. 2 for identification of core zones. 3.1.6-1 Reactor fuel cycle 3.1.6 Burnup results The time history of the fuel cycle in the DMSR provides some insight into the uranium resource utilization in this concept. The available reactivity in the core (Fig. 5) shows an increase during the first year as the inventory Of 233u, mQ%e efficient fuel than 235u, builds. 'PkiS rise would have to be controlled so that fuel consumption was ~ inhi~ed, Thus, a temporary removal of some denatured fuel or additions of fertile material might be more effective than insertion of simple neutron p~lsons. After the first year, the reactivity begins to decline as fission-product poisoning increases ana overcomes the 234~ effect. quently kept above 1.0 by periodic additions of makeup fuel, containing 20% enriched 235~. Reactivity is subse- The net conversion ratio of the system (fissile production divided by fissile consumption), which is shown in Fig. 6, undergoes a much more persistent rise that lasts about five years before a gradual decline sets in that Basts until the end of the %@=-year cycle. Much of this decline is attributable to neutron p~isoning by 238U9 which is added with the
Page 1: i *w . . I
Page 5 and 6: P iii CONTENTS ....................
Page 7 and 8: CONCEPTUAL DESIGN CHARACTERISTICS O
Page 9 and 10: 3 The primary purpose of this study
Page 11 and 12: .. .... . w..w c Y ... . r 5 2. GEN
Page 13 and 14: ii.... :.: ..... .,. \ ..... %& . 3
Page 15 and 16: addition StathQR would be required.
Page 17 and 18: !I \.... . , . ~ .... .. . . / I I
Page 19 and 20: ... .. ...... . . . $i 13 Table 1.
Page 21 and 22: 15 Initial scoping studies showed t
Page 23 and 24: .. . E 6> I S N 0.45 k- 0.50 B --.
Page 25 and 26: :.:..y ,. . . w, E9 The code calcul
Page 27 and 28: h 3. Additional 238Y is added as re
Page 29 and 30: ...z,y .. . c .A, Table 9. Actinide
Page 31 and 32: ';x.w' .... Relative power distribu
Page 33: ........ . . . :..i 27 a Inner 2.54
Page 37 and 38: ob E 2 a 4 5 6 7 8 9 10 11 12 13 14
Page 39 and 40: .. . . . . . . . . . 'a# 0.1 0.2 0.
Page 41 and 42: 35 (Doppler effect), (2) changing t
Page 43 and 44: where Ci = relative delayed-neutron
Page 45 and 46: .... . . . . , c.y..p c "
Page 47 and 48: .... :...w . . . . . :, %. , dimens
Page 49 and 50: ,. ::.y ~. . .... , 40 0 43 1 2 3 4
Page 51 and 52: .,.,. . . ., , .. . . . . . . . %..
Page 53 and 54: .... ... . ....... . .%.W 3.3.1.1 C
Page 55 and 56: 49 Variation of fuel composition wi
Page 57 and 58: .. .*,p. . . . . . . . Table 25. Ph
Page 59 and 60: ;: c.... x. . w ..i 53 Table 26, St
Page 61 and 62: would be expected to have an equili
Page 63 and 64: .... . . . . :i ,.*,&s 57 Corrosion
Page 65 and 66: . ;;..,..I . . . . . . "LW 0 9 m -
Page 67 and 68: of the fissioned atom. ea ~arly ass
Page 69 and 70: 63 n e results of a program of solu
Page 71 and 72: 65 Table 27. Sources and rates Sf p
Page 73 and 74: operation of the PISRE. 67 analyses
Page 75 and 76: UP3/UF4 ratio would be possible. DM
Page 77 and 78: $ .p9 3.3.3.1 Preparation of initia
Page 79 and 80: 73 Contamination of fuel by seconda
Page 81 and 82: *w- through the walls of the primar
Page 83 and 84: 77 4 will apparently be necessary (
Page 85 and 86:
such contamination. For a demonstra
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8% 3.4 Reactor Materials Although s
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: ....., . .’ -. ..WY used in the
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..... i.. ....., . .Yd 85 QRPIL-DWG
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... w . . .y and to salt containing
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With the different ~Bjectives of ns
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t.;$- ... quite different from thos
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93 during noma1 operation. Minor am
Page 101 and 102:
............. . . .. . .=w as SSm,
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. . . :.w . . . . , 4. ALTERNATIVE
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.. . ... . . . . . . .. . . "W 3. T
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.,.. w .." by removing some uranium
Page 109 and 110:
, . . . . . . , -c%w probably still
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and the ~ dvent (or carrier) salt a
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BO 7 TPle fuel makeup requirements
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5. CQPIPIERCIWLPZATION CONSIDERATIO
Page 117 and 118:
11% At the close of MSRE operation,
Page 119 and 120:
12YS 75 22”” 955 30” 1””
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115
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aa 7 some components in common with
Page 125 and 126:
Ae eo un t No * Table 3%. Capital c
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- ,.,.,.,., p .. ..... . G is based
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123 Table 34. Summary of annual non
Page 131 and 132:
...... . . . . ., x.:w* 4 i.. ... _
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E2 7 There are no detailed estimate
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129 particularly if such activities
Page 137 and 138:
. ~.........* . . . . . :*. ... . -
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. .. . . . . . . . ;.:w b 133 the i
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_... ..&/ ; .; with reactor scram m
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137 includlng $900 million for the
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139 The authors want to acknowledge
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. ... . .,.,.,.,.,. . , i.rc- q....
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.:. _.i .. ..... -.=* 45. A. L. Mat
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...... &;.& 3 14 5 74. W, R. Grimes
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p 103. 6. Re Hudson 11, CQNCEPT-5 U
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... . . . . . . . , . ,.Y&fl 149 ap
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Account No. -0- Three- digit digit
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.... ..
Page 162:
156 77. He 6. MacPherson, Institute
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