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

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& w :.:. . . . :,. Contract No. W-7405-eng-26 Engineering Technology Division CONCEPTUAL DESIGN CHARACTERISTICS OF A DENATURED MOLTEN-SALT REACTOR WITH ONCE-THROUGH FUELING J. R. Engel W. W. Grimes H. F. Bauman H. E. McCoy J. F. Bearing W. A. Rhoades Date Published: July 1980 NOTICE This document contains information of a preliminary nature. It is subject to revision or correction and therefore docs not represent a final report. Prepared by the OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the BEPARTNENT OF ENERGY ORNk/TM-7207 Dists Category uc-76
Page 1: i *w . . I
Page 6 and 7: iv Page 109 109 110 110 112 lb4 614
Page 8 and 9: 1 e INTRODUCTION Molten-salt reacto
Page 10 and 11: and demonstration (RD&D) program; a
Page 12 and 13: 6 2. I Fuel Circuit The fuel circui
Page 14 and 15: 8 DMSR, the shutd~wn residual-heat-
Page 16 and 17: 3. REFERENCE-CONCEPT DMSR A prelimi
Page 18 and 19: 12 2. The radial reflector is graph
Page 20 and 21: 14 The size of the core was determi
Page 22 and 23: Table 5. XSDREU' 123-gKOug energy s
Page 24 and 25: Energy group Energy range Fast 14.9
Page 26 and 27: 20 Cell material Energy Core zone I
Page 28 and 29: 22 The fit to data representing fou
Page 30 and 31: 24 Table 10. Nuclide concentrations
Page 32 and 33: 26 The absolute maximum fast flux i
Page 34 and 35: 28 Table 14. Effect of nuclide dens
Page 36 and 37: t != 1 + o= $5 56 c < 2.5 w- 1- m"
Page 38 and 39: 32 "spent" fuel. If credit were all
Page 40 and 41: 3.1.7.1 Material reactivity wsrths
Page 42 and 43: 36 immediately because of depositio
Page 44 and 45: 38 Table 22. Kinetic response of BM
Page 46 and 47: 40 of-50"C would be +0,004 (about 1
Page 48 and 49: WJDEL SECTION FOR T! i E R M A L_ A
Page 50 and 51: 44 3. EXTERIOR SALT CHANNEL TEMPERA
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[-SO0 kPa (130 psi)]. analysis were
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48 ThG 4174 IF Bei= CQrreSpOnding t
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50 Table 24. Approximate heavy meta
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52 preparation in a pure homogeneou
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54 UF~ value of Table 26 (if the UF
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56 to bring that understanding to t
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58 of the reactor. The rate of tran
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60 3.3.1.4 Operational c~nstraints
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62 These early tests seemed to show
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64 TE M PE R ATU R E ( O6 1 800 700
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4 Q‘7 40” OWL-DWG 68-10155R 0 4
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68 3, The mobility of the pod of no
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3,3,2.5 Uncertain features Prom the
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surface. 72 Outgassing sf the moder
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74 because of the marked reactivity
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3-3.3.3 Fuel maintenance ol3tions a
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nium. 78 Tt?e original charge of fu
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600°C (see Fig. 11). veloped for a
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82 (primarily by welding) into an i
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84 and there was never any evidence
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CRACKING 600 PARA M E T E W [FREQUE
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SM-I AT-d-! A -----? -I- I A 25 I
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was estimated to be the fluence at
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92 cooled drain tank. The system pr
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94 A major feature of the DMSR is t
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96 233U production capability would
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98 All the MSR options from the bre
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100 4,1.2 Converter operation with
Page 108 and 109:
102 developed far enough to lead to
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104 Step 9. Precipitate the cerium
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106 Table 29, Performance data for
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esponsibility for a chemical proces
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110 5.1.1 current status MSW develo
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112 The concept of the DMSR has emp
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114 5.2 Reactor Build Schedule 5.2.
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116 The construction cost of the MS
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118 Table 31. Bases for capital or
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120 storing the blowdown mterialb t
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122 Table 33. Staff requirement for
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124 large uncertainty is present in
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fuel would remain in the reastor dr
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128 the letter, of NRC requirements
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LWR. However, considering the mecha
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neutronic losses to 233Pa. 3-32 clu
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of the salt, which would have to be
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educe the average demand for mined
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138 probably could be developed in
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1. 2. a. 4. 5. 6. 7. 8. 9. 10. 11.
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31 e 32 8 33 0 34 35 a 36 m 37. 38
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59. 60 * 61 e 62 e 63 B 64 0 65. 66
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146 88. A. D. Kelmers et ale, Evalu
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. _. . . . . . .. .
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...... ... ........ . rrrrr, Table
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,.._ 1 . ... .. . i.iiiiii Date 197
Page 161 and 162:
1. 2. 3. 4-8. 9. 10. 11. 1%. 13. 14
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