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32 "spent" fuel. If credit were allowed for the residual fissile uranium in the salt (plutonium presumably would not be recovered), the net U308 requirement would be reduced by almost one-half, The temporal distribution of fuel requirements in a DMSR is also significant. The data in Table 17 show that only about 36% of the makeup fuel is required during the first 15 years of the cycle; the major demand occurs toward the end-of-life. Thus, if the reactor were operated at a lower capacitv factor in later years, the U308 requirement could be reduced further or the plant calendar lifetime could be extended. The ad- vantage associated with the time distribution of the makeup fuel requirement is partly offset by the large initial fuel loading and the high in- plant fissile inventory. Therefore, an optimum fuel cycle might coneeiv- ably balance a Power initial loading (and inventory) having a lower net conversion ratio against a higher requirement for makeup fuel. pears to be some latitude for optimization of the fuel cycle in this area. 3.1.6.2 Potential for imDrsvement * There ap- mile the fuel utilization of this conceptual system compares favor- ably with that of other reactor systems, some further improvements may be possible. Only a limited range of fuel volume fractions and core zone sizes has been conside~edl for this core, and other values could lead to higher performance. However, there appears to be little potential benefit in using more than two core zones. The actinide content of the salt is thought to be near optimum for long-term, high-performance conversion, but, as implied previously, an- other concentration might be better for the 30-year cycle. Certainly, some improvement in fuel utilization would come from relaxing the requirement for 2 3 8 ~ content either of the system in operation or of the makeup material being added. Table 18 shows the approximate effect of these constraints on 2 3 5 ~ requirements. fully denature the makeup feed material has only a small effect on the fuel requirement. Removing the requirement to Similarly, increasing the allowed enrichment of 234U This is frequently done in electric power stations as newer and dk cheaper plants are built.
.. . . . . . . . . . 'a# 0.1 0.2 0.4 0.2 0.2 0.2 8.2 0.2 0.2 0.2 I 33 Table 18. Effects of denaturing on 30-year cycle performance 0.2 0.142828 0.2 0.142828 0.2 0.142828 0.2 0.071414 0.2 0.142828 8.2 0.285656 8. B 0.142828 0.2 0.142828 0.4 0.142828 I 1 1 I 3450 3450 3450 3450 3450 3450 3980 3450 3040 2800 2800 %enotes reference conditions. 5120 4470 4260 4470 4470 4470 5120 4470 4670 4040 2800 $ma 9928 7710 8120a 7920 7920 9100a 7920 7710 6860 5600 in the coke has little effect. Only complete removal of all enrichment constraints would achieve an important fuel saving of 29%. Thus, the requirement for denaturi~g cannot be regarded as an overriding limitation on the potential performance of this fuel cycle. 3.1.7 Dynamic effects The dynamics of the DMSR would be dominated by the following factors: 1. a prompt, negative fuel-temperature coefficient of reactivity; 2. a slow, positive moderator-temperature coefficient ~f reactivity; 3. a negative fuel-salt density coefficient of reactivity; 4. an interaction between fuel-salt flow rate and the neutronic response of the core caused by the sweeping of delayed neutron emitters out of the core; 5. a long fuel-salt residence time in the core (relative to the average neutron lifetime).
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 and 34: ........ . . . :..i 27 a Inner 2.54
Page 35 and 36: 29 Table 16. Effect of neutron spec
Page 37: ob E 2 a 4 5 6 7 8 9 10 11 12 13 14
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
Page 99 and 100:
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
Page 141 and 142:
_... ..&/ ; .; with reactor scram m
Page 143 and 144:
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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