ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

More documents

Recommendations

Info

t != 1 + o= $5 56 c < 2.5 w- 1- m" 4 - 30 ORNL-DWG 804266 ETD FIRST FUEL 4 5 0.0 0 1 2 3 OPERATING TIME (yri 4 5 Fig. 5. Time variation of core reactivity in a once-through BMSR operating at 75% capacity factor. no OHNL -DVG 80-4267 FVD I I I 1 0 20 30 OPERATING TIME (vr) Fig. 4. Conversion ratio vs time, makeup fuel. The lifestme average conversion ratio for the 30-year fuel cycle is ekose to 0.8. The schedule of fuel additions, including the initial critical loading for a 1-GWe plant operating at a 75% capacity factor is shown in Table 17. This table also includes the quantities of the U308 and separative work required to supply the fissile materialie ~hus, the lifetime re- quirement would be about 2688 tons of U308 i f m credit were allowed for the end-of-life fissile in~entory. However, uranium is readily r&coV~B"- able from this fuel in a pure and reusable fom as LEge The recovered uranium would have to be reenriched, either by isotopic separation or by addition of high-enrichment fuel, before it could be reused in another DMSR, but reuse in some manner might be preferable to discarding the
ob E 2 a 4 5 6 7 8 9 10 11 12 13 14 15 16 17 1% 19 20 21 22 2% 24 25 26 29 28 29 31 Table 17. Fuel addition schedule for once-thrsugh BMSR 14,800 0 174 105 890 0 822 6 82 2 822 6 822 82 2 822 82 2 822 0 822 822 822 82 2 82 2 822 822 822 822 822 822 82 2 822 3,450 0 0 0 203 0 203 0 203 263 0 2 03 203 2 03 203 2 03 0 283 203 203 203 283 203 283 2 03 203 203 203 203 2 03 788 0 0 0 46.4 0 46*4 0 46.4 46.4 6 46.4 46.4 46.4 46.4 46.4 0 46.4 46.4 46.4 46.4 46.4 46.4 46.4 46. 4 46.4 46.4 46.4 46.4 46.4 789 0 0 0 46.4 0 46.4 0 46.4 46.4 0 46.4 46.4 46.4 46.4 46.4 0 46.4 46.4 46.4 46.4 46.4 46.4 46.4 46.4 46.4 46.4 46.4 46. Pa 46.4 Total 32,400 7 920 1,810.6 1,810.0 a ~~~~ bInitial loading. -~ 6 Eag = 1.182 short tons.
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: 29 Table 16. Effect of neutron spec
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
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
show all

ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?