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52 preparation in a pure homogeneous form for introduction into the reactor. In addition, the fuel must (1) be compatible with the structural and the moderator materials during normal operation, (2) be stable to intense radiation fields, and (3) tolerate €issfon of uranium and plutonium and the development of significant concentrations of fission products and p%tttomium and other actinides. Also, without dangerous consequences, it must be able to withstand a variety of off-design situations such as heat-exchanger leaks or possible ingress of air. Finally, although not presently necessary, it is desirable that at end-of-life the fuel be ame- nable to recovery of fissile, fertile, and other valuable materials. The ability of the fuel to meet or not to meet these diverse and conflicting demands largely depends on the chemical properties sf the fuel. ~ost of the details of fission-prsduet behavior are deferred to a subsequent sec- tion, but much of the basis for expected fuel performance is presented in the foBkowing discussion. Thermodynamics of molten fluoride solutions. The thermodynamic properties of many pertinent species in molten LIF-BeF2 solutions and a smaller number in LiF-BeF2-ThFq solutions have been studied in a long- continued experimental program. A variety of experimental techniques was employed. Much of the data was obtained by direct measurement of equilibrium concentrations and partial pressures for reactions such as and (where g, c, I, and d represent and solute respectively) us%ng dium. Maray studies of solubility behavior of sparingly s~l~ble fluoride species have also been made, 13aes25926 has reviewed all these studies amd has tabulated themodynamic data for many species in molten Li2BeFq. Table 26 shows values for standard free energy of fomstfsm of major constituents and s~me possible corrosion products. has also . ,. . . . . . .. x;&.;* .
;: c.... x. . w ..i 53 Table 26, Standard free energies of formation for compounds dfsssPved in molten Ei2WeP4 a -141.79 16.58 -243.86 30.01 -338.04 40.26 -445.92 57.85 491.19 62.50 -452.96 65.05 -146.87 36.27 -154.69 21.78 -171.82 21.41 180.4 98,5 108.8 evaluated the effect of solvent composition in the EiF-BeF2 system ow activity coefficients of a variety of solutes. Using a sophisticated spectrophotometric analysis for UF, and UF3$ more recent study by Gilpatrick and Tsth to evaluate the equilibrium 1 T + UF,(d) W(d) + c d in several LiF-BeF2 and LIF-BeF2-ThF4 solvents essentially confirmed the 98.6 57.1 67.5 76.3
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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 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: .. .*,p. . . . . . . . Table 25. Ph
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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