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36 immediately because of deposition of energy by fast neutrons and prompt gammas, Because the heat capacity of the moderator in a zone is always at least five times that of the fuel, the effect of direct transient mad- erator heating would be negligible. The reflector and vessel coefficients would probably be very slow in taking effect because of large heat capacities and Pow fuel flow rates. Their total is dominated by a negative expansion tern. 3 0 1 e 7 B 3 Belayed-neutron effects Table 21. Delayed-neutron fraction, 6 Contributor Fissiom fraction Contribution t o B 2 q J 0,55 235~ 0.23 B1 u e. oni urn 0.22 0.0014 Q.OOP5 0 * 00046 Total B 0.0034 An unusual aspect of MSRs 1s that the fuel circulates fast enough to remove significant numbers of delayed-neutron precursors from the core be- fore the neutrons are emitted. The Lmped-parmeter kinetics equations are taken as and .. .... ,. . ., ".IW
where Ci = relative delayed-neutron precursor concentration, t = time, B = reactor power, B = delayed-neutron fraction, k = muPtipLieation factor, 37 h = prompt-neutron generation time, xi = aeiayea-neutPon prec~rsor decay constant, ai = delayed-neutron fractional yield, R = coolant flow constant, T = mean salt transit time in external loop. These equations then show that, where dollars of reactivity are defined as $i = (k - l)/kB, the steady balance condition requires a nonzero value of $ e Thus, 'Ai' where E5 is equal to 1 - e . Defining a new effective reactivity as we can write the inhour equation relating asymptotic inverse period w to A, the amount of reactivity in excess of that required to maintain steady state under the given flow rate. where Fi is equal t o 1 - e~p[--CAi 9 U)T]. The prompt-neutron generation time was calculated by the boron-poison method to be 362 ps. For now, we will ignore the difference between B and Beff, which is expected to be small fn Bow-leakage systems. Table 22 was compiled using standard
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 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: 35 (Doppler effect), (2) changing t
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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