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

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4 Q‘7 40” OWL-DWG 68-10155R 0 40 28 30 40 50 60 70 EO 90 100 440 420 130 140 (50 460 470 480 490 200 216 DEPTH IN FQAPHITE (mils) Fig. 14. Fission product distribution in CGB ($55) graphite specimen 79 3sed in MSWE core during 32,000 sf power operation.
operation of the PISRE. 67 analyses for 1311 showed that a large fraction of the iodine was present in the fue120~72 and that 1311 deposited on metal or graphite surfaces in the core region. However, material balances for were generally low. ~t is possible that some of the precursor, 131~e (25 min), was volatilized and sparged with the krypton and X~H~QR. Fur- ther, 1 3 1 ~ produced by decay of E ~ I T in ~ complex metallic deposits (as in the heat exchanger) may not have been able to return to the salt. Noble and seminoble fission products. Some fission-product metals (~e, AS, Nb, m, RU, ~ h Pa, , Ag, cd, SW, and sb) have fluorides that itre unstable toward reduetion by fuel mixtures with appreciable eoncentra- tions of UPQ; thus, they must be expected to exist entirely %n the ele- mental state in the reactor. Selenium and tellurium were also expected to be present as elements within the reactor circuit, and this behavior was generally csnfirned during operation of the MSRE. 19920 $72 he MSRE fuel samples usually contained far less than the generated quantities of these elements. Portions of the MSRE samples were found (probably as metalPic particulates) in the helium sparge gas,* deposited on metal surfaces, and (a reasonably small fraction) deposited on graphite specimens. However, the distribution and especially the inventory in the fuel at the sampling point in the pump bowl showed major variations. Further study will be necessary before details of their behavior can be predicted with confidence for a DMSR. ~n general, the results from MSRE operations suggest the following,20 I. The bulk of the noble metals remain accessible in the circulating loop but with widely varying amounts in circulation at any particular time. 2. In spite of this wide variation in the total amount found in a particular sample, the proportional composition is relatively constant, indicating that the entire inventory is in substantial equilibrium with the new material being produced. 2k Much-improved gas-sampling techniques used in later stages of MSRE operation showed the fraction carried in the gas to be less than 2% of the quantity produced” (with the possible exceptton of il i: 3% of ko3~u).
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P iii CONTENTS ....................
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CONCEPTUAL DESIGN CHARACTERISTICS O
Page 9 and 10:
3 The primary purpose of this study
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.. .... . w..w c Y ... . r 5 2. GEN
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ii.... :.: ..... .,. \ ..... %& . 3
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addition StathQR would be required.
Page 17 and 18:
!I \.... . , . ~ .... .. . . / I I
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... .. ...... . . . $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 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: 65 Table 27. Sources and rates Sf p
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
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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
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123 Table 34. Summary of annual non
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...... . . . . ., 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
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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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.... ..
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156 77. He 6. MacPherson, Institute
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