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

More documents

Recommendations

Info

112 The concept of the DMSR has emphas-ized proliferation resistance, and further design efforts would be expected to adhere to proliferation- resistance criteria. However, no major areas have been identified in which the R&D requirements for a DNSR would be substantially different from those for other versions of the MSR concept. Essentially the same R&D program would be pursued as was planned for the MSBR. The se1eetFon of a low-power-density core for the DMSR has relieved the requirements fur core graphite (espectally for gas permeability) and has simplified vessel design (because graphfte replacement is not required). a reference DMSR without on-line fuel processing has removed the development of on-line processing from the expected critical path for reactor development. Processing development should proceed, however, to meet two clQsely related objectives: (I) development of on-line reprocessing to obtain the improved fuel utilization of the break-even breeder DMSR op- tion as soon as possible and (2) development ~f a process (probably using the same basic technology) for eventual central processing of fuel from once-through DMSRs, possfbly in secure fuel service centers. plan.”‘ 5.1.3 Base program schedule and costs The selection of h R&D base program has been presented in some detail in the program me projected cost schedule (in 1978 dollars) for each major development activity annually from 1980 to 1994 and as a total for 1995 through 2011 is given in Table 30. The complete base program is projected to cost about $700 million over about 30 years. Some of the costs are targeted for elether the Molten-Salt Test Reac- tor (MSTR) or the demonstration DXSR (as discussed ita the following sec- tion), while other costs apply generally t~ the MSR develupment program. However, these costs do not include design and construction costs for the reactor plants The schedule of fuel processing technology development was set up for the concurrent development of on-line processing. This schedule could be stretched if the once-through cycle were chosen for the first DMSRs. How- ever, the development of processing technology is an important goal of the program in any event. e
12YS 75 22”” 955 30” 1”” 7462 Table 30. Projected research and develnpnent costs for XSR base development program 61” RZ” 95” 1,175 2,070 :,xlo 2,170 2,;s” 2,455 1,060 12,750 b 0 i,Y”” 3,c25 3,590 1,170 1,502 507 30” 45” 6”” 75 1°C 15” 13,968 2R,ZWb l4,Rl” (Thousands of 1918 dollars) 93” 765 6”” 4”” 7”” 4”” 35” 25” 2, SF”” 1,“““(1 3,230 3,670 51” 0 xl” ion 1,755 :,h12 1,560 i,i3* :69 15” lib 137 5”” 6”Q 65” 5% :co 13” 1”” 1”” 95,s:ot L7,29hh 18,8?6 ?C,ZSI
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 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 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: 11% At the close of MSRE operation,
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
show all

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

Create successful ePaper yourself

Delete template?

Save as template?