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3. REFERENCE-CONCEPT DMSR A preliminary conceptual design has been developed for a DMSR oper- ating on a 30-year fuel cycle. The emphases to date have been on the reactor core design and fuel cycle, with less attention to other aspects of the system. Although thfs design establishes the basis concept and char- acterizes its major properties, it is tentative and would be subject to major refimement and revtsion if a substantial design effort were under- taken. 3.1 Neutronic Properties The basic features of this BMSR concept which distfnguish it from other MSRs are established primarily by the reactor care design and its ass~ciated neutronic properties. 'Phe design described here represents the results of a first-round effort to balance some of the many variables invo%ved in a reactor COT@, but it is by PPO means an opthized design. 3.1.1 Weutronics core model Prom a neutranics point of view, the core is simply designed as f ~l- EoWs (FJg. 2). 1. The core and r@f%e~tor fill a right circular cylinder that is 18 rn in diameter and 18 m high. The core, which is a cylinder 8.3 m in diameter and 8,3 m high and centered inside the larger volume, fs filled with cylindrical graphite logs in a triangular array of 8.254-m pitch. Approximately 95X of the CQF~ (core B) has log diameter of 0.254 m, with the fluid fuel filling the interstftial volume to praduce a fuel volume fraction of 9.31%. An axial cyLindrieal hole of 0,851-m diam in the een- ter of each log admits another 3.63% fuel for a total of 12.94 voP %. To achieve flatteni~g of the fast flux and thus maximize the lifetime of the graphite moderator, the remaining 5% of the core (core A>, a cylinder 3 m in dfameter and 3 m hfgh, has a log diameter of 0.24 m, resultfng in a total fuel volume fraction of 20.00% in this zone.
!I \.... . , . ~ .... .. . . / I I RADIAL GAP CORE B MI BPLANE BOTTOM PLENUM BOTTOM REFLECTOR -1.50- B).Q5=+ 4 4.15 I ORML-DWG 80-4263 ETD Fig. 2. DMSR core model for neutronic studies - eylindrfcal geomgtry Call dimensions in meters).
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: addition StathQR would be required.
Page 19 and 20: ... .. ...... . . . $i 13 Table 1.
Page 21 and 22: 15 Initial scoping studies showed t
Page 23 and 24: .. . E 6> I S N 0.45 k- 0.50 B --.
Page 25 and 26: :.:..y ,. . . w, E9 The code calcul
Page 27 and 28: h 3. Additional 238Y is added as re
Page 29 and 30: ...z,y .. . c .A, Table 9. Actinide
Page 31 and 32: ';x.w' .... Relative power distribu
Page 33 and 34: ........ . . . :..i 27 a Inner 2.54
Page 35 and 36: 29 Table 16. Effect of neutron spec
Page 37 and 38: ob E 2 a 4 5 6 7 8 9 10 11 12 13 14
Page 39 and 40: .. . . . . . . . . . 'a# 0.1 0.2 0.
Page 41 and 42: 35 (Doppler effect), (2) changing t
Page 43 and 44: where Ci = relative delayed-neutron
Page 45 and 46: .... . . . . , c.y..p c "
Page 47 and 48: .... :...w . . . . . :, %. , dimens
Page 49 and 50: ,. ::.y ~. . .... , 40 0 43 1 2 3 4
Page 51 and 52: .,.,. . . ., , .. . . . . . . . %..
Page 53 and 54: .... ... . ....... . .%.W 3.3.1.1 C
Page 55 and 56: 49 Variation of fuel composition wi
Page 57 and 58: .. .*,p. . . . . . . . Table 25. Ph
Page 59 and 60: ;: c.... x. . w ..i 53 Table 26, St
Page 61 and 62: would be expected to have an equili
Page 63 and 64: .... . . . . :i ,.*,&s 57 Corrosion
Page 65 and 66: . ;;..,..I . . . . . . "LW 0 9 m -
Page 67 and 68:
of the fissioned atom. ea ~arly ass
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63 n e results of a program of solu
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65 Table 27. Sources and rates Sf p
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operation of the PISRE. 67 analyses
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UP3/UF4 ratio would be possible. DM
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$ .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
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: ....., . .’ -. ..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,
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. . . :.w . . . . , 4. ALTERNATIVE
Page 105 and 106:
.. . ... . . . . . . .. . . "W 3. T
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.,.. w .." by removing some uranium
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, . . . . . . , -c%w probably still
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and the ~ dvent (or carrier) salt a
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BO 7 TPle fuel makeup requirements
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5. CQPIPIERCIWLPZATION CONSIDERATIO
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11% At the close of MSRE operation,
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12YS 75 22”” 955 30” 1””
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115
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aa 7 some components in common with
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Ae eo un t No * Table 3%. Capital c
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- ,.,.,.,., p .. ..... . G is based
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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
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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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.... ..
Page 162:
156 77. He 6. MacPherson, Institute
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