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22 The fit to data representing four E-~KWV~E times from five years to infinity had an absolute standard deviation of 6.28%, which was considered adequate. Studies using this model indicated that removal times of a few years but shorter than infinity were not worthwhile, and the results of this section assume R = 0. 3-1 e 4.3 Trans~lutonium ef f ects A detailed study of transplutonium effects9 was made, and the con- chsion was reached that the resulting fissile production only partially offsets the capture. The balance is less favorable than in reactors of higher power density because of the partial ~ ~ecay of 244~1~ to 2 4 0 which ~ ~ ~ has comparatively less value. produced from 23%~ is joined by 0.11 additional atoms from the decay of 244~me plutonium effect, 4.0 additional absosptio~~s and 3.2 additional. fission neutrons ultimately result. me study showed that each atom of 2 4 0 ~ ~ FOP each neutr~n absorption in 242~u ca~culated without the trans- Although the actual time effects are complicated, the net effect was approximately represented as an additional fictitious ~uclide, which was produced by capture in 2‘’~u and had the absorption cross section of 242~u and no progeny. This would be slightly conservative at equilibrium and probably at earlier times also. 3. E. 5 Static neutronic results Table 9 indicates the inventory of actinides at the beginning, mid- dle, and end of the 30-year operating period, assuming a 752 capacity fac- tor. The high initial loading of 235U is largely replaced by 233U bred by the system in the first half of the lifetime. Toward the end of lifetime, enriched uranium additions required to override fission-product buildup cause a final increase in both the 23% and 238U content. The plutonium inventory is never Barge because of its high cross section in this spec- trum. Table 10 shows the midlife neutron utilization infomation. Yste the low capture rate in nonfuel salt constitu@nts (O.Ol53) and the fission-
...z,y .. . c .A, Table 9. Actinide inventories in DMSR fuel salt Total actinides Fissile uranium Total fissile product capture rate (0.0563). 110,800 0 0 8 3,450 0 0 %4,000 0 0 0 0 0 127 9 000 3,450 3 9 450 Inventory (kg) 103,000 45 1,970 372 1,020 661 75 19,608 179 IO2 76 99 36 127 000 2 990 3 440 92 * 900 38 1,910 596 1 9 250 978 136 28 9 608 23 1 B 33 100 179 93 127 9 000 3,160 3 , 490 place in 238~ and its progeny, even though they comprise only 9.8% sf the fissile ~ I I V ~ I I ~ Q In ~ ~ spite . of the high value of v for these nuclides, they would not be a sufficient fuel without the thorium chain. The slight contribution of the transplutonium nuclides to total mass has been ignored, and the absorption value shown for this nuslide group is a net of absorp- tions less fissions. 241~m, a poor fuel. me capture in 234~a is particularly expensive because each such atom otherwise would result in a highly profitable 233U fission. A total of 22.2% of the fission take A ~ O U 4% ~ of the 2bl~u is lost through decay to
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: h 3. Additional 238Y is added as re
Page 31 and 32: ';x.w' .... Relative power distribu
Page 33 and 34: ........ . . . :..i 27 a Inner 2.54
Page 35 and 36: 29 Table 16. Effect of neutron spec
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
Page 87 and 88:
8% 3.4 Reactor Materials Although s
Page 89 and 90:
: ....., . .’ -. ..WY used in the
Page 91 and 92:
..... i.. ....., . .Yd 85 QRPIL-DWG
Page 93 and 94:
... w . . .y and to salt containing
Page 95 and 96:
With the different ~Bjectives of ns
Page 97 and 98:
t.;$- ... quite different from thos
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93 during noma1 operation. Minor am
Page 101 and 102:
............. . . .. . .=w as SSm,
Page 103 and 104:
. . . :.w . . . . , 4. ALTERNATIVE
Page 105 and 106:
.. . ... . . . . . . .. . . "W 3. T
Page 107 and 108:
.,.. w .." by removing some uranium
Page 109 and 110:
, . . . . . . , -c%w probably still
Page 111 and 112:
and the ~ dvent (or carrier) salt a
Page 113 and 114:
BO 7 TPle fuel makeup requirements
Page 115 and 116:
5. CQPIPIERCIWLPZATION CONSIDERATIO
Page 117 and 118:
11% At the close of MSRE operation,
Page 119 and 120:
12YS 75 22”” 955 30” 1””
Page 121 and 122:
115
Page 123 and 124:
aa 7 some components in common with
Page 125 and 126:
Ae eo un t No * Table 3%. Capital c
Page 127 and 128:
- ,.,.,.,., p .. ..... . G is based
Page 129 and 130:
123 Table 34. Summary of annual non
Page 131 and 132:
...... . . . . ., x.:w* 4 i.. ... _
Page 133 and 134:
E2 7 There are no detailed estimate
Page 135 and 136:
129 particularly if such activities
Page 137 and 138:
. ~.........* . . . . . :*. ... . -
Page 139 and 140:
. .. . . . . . . . ;.:w b 133 the i
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_... ..&/ ; .; with reactor scram m
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137 includlng $900 million for the
Page 145 and 146:
139 The authors want to acknowledge
Page 147 and 148:
. ... . .,.,.,.,.,. . , i.rc- q....
Page 149 and 150:
.:. _.i .. ..... -.=* 45. A. L. Mat
Page 151 and 152:
...... &;.& 3 14 5 74. W, R. Grimes
Page 153 and 154:
p 103. 6. Re Hudson 11, CQNCEPT-5 U
Page 155:
... . . . . . . . , . ,.Y&fl 149 ap
Page 158 and 159:
Account No. -0- Three- digit digit
Page 160 and 161:
.... ..
Page 162:
156 77. He 6. MacPherson, Institute
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