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12 2. The radial reflector is graphite 0.8 m thick and is attached to the reactor vessel at the 18-m diam. This leaves a gap of 0.05 m filled with fuel salt surrounding the core laterally. 3. The inlet and outlet plena cover both the core and radial gap to their full diameter and are each 0.28 m thick. They consist of 50% struc- tural graphite and 50X fuel. 1Q-m diam. 4. The axial reflectors are each 0.65 m thick and extend to the full 5. All reflector regions contain a small amount of fuel salt for cooling, which is estimated as 1 vol X at operating temperature. 6. All stated dimensions are assumed to apply at nominal operating conditions. During system heatup, the length and diameter of the core vessel are assumed to increase at the rate of expansion of Hastelhy-N. The reflectors are assumed to expand at the expansion rate of graphite but to remain attached to the vessel. Because graphite expansion is less than that of the vessel, this will result in admatting additional salt to the reflector zones. The core and plenum regions are assumed to expand radially only at the expansion rate of graphite, which will establish the thickness sf the radial gap. The axial configuration is affected by the logs floating upward in the salt and by the lower plenum being constructed so that it always contains 58% salt. The thicknesses of the core and the upper plenum, then, increase at the graphite expansion rate, but the lower plenum grows at such a rate as to span the gap between the core and the bottom reflector. Mechanical properties used for the principal constituents are sum- marized in Table 1. The salt is taken to have the nominal chemical corn- position shown in Table 2. The tern "actinides'o in this study refers to all elements of atomic numbers - > 90 and not just to transplutonium ele- merits. The actinide percentage is subject to small variations depending on the fuel cycle and the history of the fuel. The inventory of- fuel salt, both in and out of the core, is summa- rized in Table 3. This is believed to be a generous estimate sf the required inventory for a I-GWe system. The thermal energy yield per fission is assumed to be 190 MeV for translation of abss%ute fission rates to ef- fective power level.
... .. ...... . . . $i 13 Table 1. Reference properties of fuel salt and moderator for a DMSR Characteristic Value 3 Graphite moderatsr density, Mglm 3 Fuel-sdt density, Mg/m Graphite linear thermal expansion, x 10-6 1.84 ~ - 1 4.1 vessel linear thermal expansion, x K-1 17.1 Fuel voPumetrie thermal expansion, x K-’ 208 Table 2. Nominal chemical composition Of DMsR fuel salt Mat er i a1 Molar percentage k i p 74.0 BeF2 16.5 XFba 9.5 Fission products Trace a x refers to all actinides, Table 3. DMSR fuel-salt inventory Lo cation VoPume (m3> core 59.4 Top and bottom plenums 11.1 Radial gap 10.9 Re f 1 e c tors 3.0 External loop 20.0 104.0 3, lo
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: !I \.... . , . ~ .... .. . . / I I
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 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
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73 Contamination of fuel by seconda
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*w- through the walls of the primar
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77 4 will apparently be necessary (
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such contamination. For a demonstra
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8% 3.4 Reactor Materials Although s
Page 89 and 90:
: ....., . .’ -. ..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,
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””
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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
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.. ... _
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E2 7 There are no detailed estimate
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129 particularly if such activities
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. ~.........* . . . . . :*. ... . -
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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
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
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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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