ORNL-5388 - the Molten Salt Energy Technologies Web Site

More documents

Recommendations

Info

C-8 Table C-5. Energy Support Ratios in Year 2050 for Various Nuclear Policy Options (Support Ratio = Installed Nuclear Capacity Outside Ener y Center/Installed Nuclear Capacity Inside Energy Center B Advanced Support Ratlo Converter Ootion 1 E* 1 2 3 4 5u 5T 6 7 8 *System with standard LWR only. m 1.54 m 1.47 m 0.49 m 0.24 m 2.42 m 2.10 m 1.85 m 1.77 High-Cost U308 Supply 0.72 m 5.69 3.74 0.76 m 6.33 3.86 0.92 m 5.79 3.07 0.24 * 4.02 2.50 Intermediate-Cost U308 Supply 1.65 m 5.06 5.05 1.65 m 4.78 4.78 0.94 m 4.03 3.84 1.82 m 3.30 3.20 As pointed out previously, with only 3 million ST of U308 available below $160/lb, the only systems that satisfy the energy demand of 350 GWe in the year 2000 and 15 GWe/yr thereafter are those with breeders. The disadvantage of the classical Pu-U breeder cycle (Option 3), of course, is the low energy support ratio since the pl'utonium that is produced must be used in the energy centers. One technique for increasing the energy support ratio is to load thorium in the blanket of these breeders, while retaining plutonium and uranium in the cores. The 233U that is produced in the blankets is then burned in denatured LWRs located outside the centers (Option 6). The resulting energy support ratios for Option 6 vary from 1 to 2, depending upon the advanced converter option. Option 7 introduces a denatured FBR which would provide 233U to the system and therefore should increase its nuclear growth potential. demand itself, the addition of the denatured breeder in Option 7 actually had a minimal impact. 1.27 2.13 1.07 1.26 5.37 4.78 1.03 However, since Option 6 can meet the projected nuclear growth The energy support ratios of Options 6 and 7 could be further increased by replacing the uranium in the core of the Pu-U breeder with thorium (Option 8). With the high-cost U308 supply, energy support ratios of about 3 are obtained for this system. The introduction of thorium in the core of a breeder lowers the breeding ratio to the point that, in contrast to Option 7, significant quantities of FBRs operating on denatured fuel must be built to meet the projected nuclear growth demand. 2.74 1.46 2.13 1.06 1.28 5.37 4.78 1.04 2.74 3.09 3.27 2.89 3.11 5.49 4.78 3.07 3.62 c L L L % L c c G c c I' L c
E , 1 ' b _. I ' L 1 b _- i G i' b c-9 In general, the energy support ratio trends for the various options are the same if 6 million tons of U308 i s available below $160/lb; however, they are significantly higher, largely because more low-enriched LWRs can be built. Selected detailed results for all the cases calculated are presented in Table C-6, C-7, and C-8. While many of the numbers in these tables appear elsewhere in this report, many numbers are also shown for the first time. For example, the plant mix in year 2025 and the levelized power cost for each plant starting up in the year 2025 are shown. The purpose of these tables is to group all the data together and also to provide sufficient data to help explain the behavior of the various reactor systems. (Note: Cases 1LT and 1LTM in Table C-6 are for changing enrichment compositions; see Section 6.2-1 in Chapter 6.)
Page 1 and 2:
Interim Assessment of the Denatured
Page 3:
i L i b I, i L L bi L L Contract No
Page 7 and 8:
1, L L t i Ltr 1 L L V PREFACE AND
Page 9 and 10:
L i Li 1, I b k b id ii t L id b i
Page 11 and 12:
I L bi i; L 7.3.1. Possible Procedu
Page 13 and 14:
i xi I b L ABSTRACT A fuel cycle th
Page 15 and 16:
I b .- i, hd t t CHAPTER 1 INTRODUC
Page 17 and 18:
- - I 4d _- t .- ! Lili L Ld id .-
Page 19 and 20:
L .- k id .- I L: _ - I iclr .- i b
Page 21 and 22:
I, G - -- I id ..- ! I _. I: L _.-
Page 23 and 24:
huJ -- AI I ' b --- I bl --- t L L
Page 25 and 26:
-- t Li - I' b -. c (u I i ai L i i
Page 27 and 28:
L - i' u i Lt L r- L t- b L 2-7 den
Page 29 and 30:
2-9 1. Nuclear power is limited to
Page 31:
e Isr i L i- b t CHAPTER 3 ISOTOPIC
Page 34 and 35:
232" Fig. 3.0-1. Decay of 232U. ORN
Page 36 and 37:
3-6 3.1. ESTIMATED U CONCENTRATIONS
Page 38 and 39:
3-8 The values in Table 3.1-2 are a
Page 40 and 41:
3-1 0 3.2. RADIOLOGICAL HAZARDS OF
Page 42 and 43:
3-1 2 232u IN RECYCLED HTGR FUEL (p
Page 44 and 45:
3-14 3.2.2 Toxicity of 232Th Given
Page 46 and 47:
1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11.
Page 48 and 49:
3.18 There are three approaches whi
Page 50 and 51:
1 i i 3-20 3.3.2. Fabrication and H
Page 52 and 53:
The 3-22 3.3.3 Detection and Assay
Page 54 and 55:
3-24 3.3.4. Potential Circumvention
Page 56 and 57:
3-26 - either large centrifuge pilo
Page 58 and 59:
! 3-28 Table 3.3-3. Enriched Proauc
Page 60 and 61:
3-30 The high alpha activity of ura
Page 62 and 63:
3- 32 Table 3.3-7. Sumry of Results
Page 64 and 65:
3-34 statistical redundancy through
Page 66 and 67:
introduce time, cost and visibility
Page 68 and 69:
3-38 An additional factor relative
Page 71 and 72:
I b t I t L 1; L t ki 4.0. 4.1. CHA
Page 73 and 74:
L L _ _ { i J _- \ I b B u il c _.
Page 75 and 76:
Y m I I I . aro ID0 10.00 4-5 ORNL-
Page 77 and 78:
t .. -. F 4d -- I ' L 0- 122, L _-
Page 79 and 80:
L L; L t -I I ' b L -- t i b -- I;
Page 81 and 82:
_- I -- L i d .-- L 4-1 1 Reference
Page 83 and 84:
_- id L t I , 4d i, L id L 5 bi t h
Page 85 and 86:
-- - . & I I ' h I ' Y 61 L -- I( L
Page 87 and 88:
u -- x i I*i 1- bi 4-1 7 The use of
Page 89 and 90:
la - i , I br -_ t c c L e L 4-1 9
Page 91 and 92:
4-21 Case B" is a modification of C
Page 93 and 94:
c 4-23 L i a L L 4.2. SPECTRAL-SHIF
Page 95 and 96:
4-25 Initial analyses of spectral-s
Page 97 and 98:
h 1' b t c i--; & I- & 1: i f 4-27
Page 99 and 100:
c- i L L e I b 4-29 . safeguards fo
Page 101 and 102:
L t i- bi L L t i 4-31 a significan
Page 103 and 104:
~ kc'l c" -1 r-"! r! r-'i c Table 4
Page 105 and 106:
F-- I iJ L ii - L c c 4-35 Referenc
Page 107 and 108:
c r- L i] L h L __ f; t 4-37 trons
Page 109 and 110:
Table 4.4-1. Fuel Utilization Chara
Page 111 and 112:
L I 1 I Ld I ie i-- 1 t' 4-41 4.4.2
Page 113 and 114:
4-43 Table 4.4-4. PBR Coated Partic
Page 115 and 116:
HEU/Th 0.59 Seed i3 Breed 0.58 HEU/
Page 117 and 118:
L i; 1 I i; i 1. 2. 3. 4. 5. 6. 7.
Page 119 and 120:
4-49 Table 4.5-1. Fuel Utilization
Page 121 and 122:
ments. 4-51 The calculations for LM
Page 123 and 124:
1. 2. 3. 4. 5. 6. 7. 8. 4-53 0 77-1
Page 125 and 126:
Table 4.6-1. Comparison of Fuel Uti
Page 127 and 128:
4-57 _I 10 10' 2 2' CASE NUMBER -.
Page 129 and 130:
4-59 Most of the information availa
Page 131 and 132:
- i b k L L -- I , b -- I .- I Li L
Page 133:
4-63 on only the preliminary data p
Page 136 and 137:
c e E c
Page 138 and 139:
! 5-4 5.1. REACTOR RESEARCH AND DEV
Page 140 and 141:
5-6 As has been pointed out above,
Page 142 and 143:
5-8 the LMFBR on its reference cycl
Page 144 and 145:
5-10 The fuel performance program u
Page 146 and 147:
. 5.1.2. Government Research and De
Page 148 and 149:
5-1 4 The first aspect of large pla
Page 150 and 151:
5-1 6 and should also address metho
Page 152 and 153:
I DATA BASE DEMu)pMENT DEMO DESIGN
Page 154 and 155:
j ~ 5-20 The R,D&D costs are highes
Page 156 and 157:
5-22 In the case of metal-clad oxid
Page 158 and 159:
5-24 5.2.2. Research, Development,
Page 160 and 161:
5-26 program, including hot testing
Page 162 and 163:
c c
Page 164 and 165:
6-4 persed areas ensured - a fact w
Page 166 and 167:
6-6 6.1.2. Reactor Options The reac
Page 168 and 169:
Reactor/Cycl ea LWR-U5(LE)/U-S LUR-
Page 170 and 171:
6-10 6.1.3. Nuclear Policy Options,
Page 172 and 173:
Table 6.1-4. Nuclear Policy Options
Page 174 and 175:
SWU SWU 6-14 UZJS USILEINS WYI U5IL
Page 176 and 177:
6-16 n nM MEDL nows.1 Option 4: In
Page 178 and 179:
6-18 HM HEDL7OOl.70.3 Option 6: In
Page 180 and 181:
SRCIFIED CONSTRUCTION LlMllLD INTRO
Page 182 and 183:
50- 40 6-22 c Y \ VL - :-: F 30- -
Page 184 and 185:
6-24 The potential nuclear contribu
Page 186 and 187:
%- f $400 J 2 s 2, 1 THE LWR FOLLOW
Page 188 and 189:
141.6 ST - U308 4 7.2 lo3 swu ENRIC
Page 190 and 191:
6-30 reactor. Since this increase i
Page 192 and 193:
‘9. ,1 ST ‘3O8 6-32 12 Kg HM I
Page 194 and 195:
6-34 1HE LWR WITH FISSILE UUNIUM PC
Page 196 and 197:
THE LWR WITH PURONIUM MlNUllUTlON A
Page 198 and 199:
6-38 be located in energy centers a
Page 200 and 201:
6-40 installed capacity must be han
Page 202 and 203:
lm, 1 I I I I mf RR WITH UGHT rwrmi
Page 204 and 205:
6-44 6.2.7. Converter-Breeder Syste
Page 206 and 207:
25.2 ST swu 6-46 19 Kg fir Pu 13 Kg
Page 208 and 209:
6-48 Table 6.3-2. Summary of Result
Page 210 and 211:
6-50 (4) If all plutonium produced
Page 213 and 214:
I d r-- 1 > w I r- k z r L id r- .
Page 215 and 216:
L 1 L u without benefit of U.S. exp
Page 217 and 218:
L a, - L i -- k; L t IJ L 7-7 While
Page 219 and 220:
7-9 Viewed solely from the plutoniu
Page 221 and 222:
L L i; i; 7-1 1 routinely in LWRs a
Page 223 and 224:
'I 7-1 3 t I: k: The isotopic compo
Page 225 and 226:
U L L L L ld 1 i" * required 233U m
Page 227 and 228:
I I, i 7-1 7 ii I 1 I L L k L i Thr
Page 229 and 230:
li i i L Li L & I ' i kr ii L i h i
Page 231 and 232:
7-21 7.3. PROSPECTS FOR IMPLEMENTAT
Page 233 and 234:
L I L t L i L i 1 L 7-23 7.3.1. Pos
Page 235 and 236:
7-25 7.3.2. Considerations in Comme
Page 237 and 238:
.. I b k; L; i b b 1J I L 7-27 cycl
Page 239 and 240:
7-29 7.4. ADEQUACY OF NUCLEAR POWER
Page 241 and 242:
L i' hd .- - I ' i t L i' b i -' b
Page 243 and 244:
x ibd 1 .. I i, L -- i t Table 7.4-
Page 245 and 246: 7-35 cycled in Pu/Th converters, th
Page 247 and 248: L 1' b I_- ,- i b -- I ' b L 7-37 T
Page 249 and 250: ..a 4 I- 1 ' u c1 Y u L 7-39 betwee
Page 251 and 252: L e, I I ' lb t 7-41 Systems that u
Page 253 and 254: e-. . ! hr L3 z i- b: i- b L c i li
Page 255 and 256: 7-45 j I Table 7.5-1. Integrated As
Page 257 and 258: - isi. c ‘Id i L c 7-47 Although
Page 259 and 260: e Other e e e On the e 7-49 technol
Page 261 and 262: t a APPENDICES
Page 263 and 264: A-3 Appendix A. ISOTOPE SEPARATION
Page 265 and 266: I] 1- $i ill 8 LI b' The Gas Centri
Page 267 and 268: id A- 7 The Component Preparation L
Page 269 and 270: i ?L 1- U t L fl bi L c u La -- ti
Page 271 and 272: p; ‘U i-- L ,c c Japan A-1 1 Tabl
Page 273 and 274: 13 A-13 L" efficient of the units d
Page 275 and 276: L L L t I h h u L; _- t f is throug
Page 277 and 278: u A-1 Aerodynamic Methods 7 Both th
Page 279 and 280: i i d .- I . ii hi L i: i t ' Li 1
Page 281 and 282: la t L I I, lj ir 1 Li c I L L' B-1
Page 283 and 284: i; 1 t u 1 1 B-3 Table 8.5. Reactor
Page 285 and 286: Table 6-7. Marginal Costs of U308 a
Page 287 and 288: LJ L L1 a .E 4' P Y W 5 18 2 16 : 0
Page 289 and 290: Appendix C. DETAILED RESULTS FROM E
Page 291 and 292: 1 i; Li b L lkd t L L I hd I ' L; i
Page 293 and 294: L c-5 The introduction of the class
Page 295: i ' ibd 1 b i L L i L I Li . . b b
Page 299 and 300: -, ii I ; b i- ii L b 4 i L L i‘
Page 301 and 302: _- I ii I _ _ I L I td C i b L i, L
Page 303 and 304: Qulatiw klur W i t y hilt (*I thrmg
Page 305 and 306: L c c b - i ii L r D-1 Appendix D.
Page 307 and 308: L L L L [i i” Table D -2. Maximum
Page 309 and 310: Fig. D-2 (cont.) 25W I I I I I (I)
Page 311 and 312: [i energy center. It can be seen fr
Page 313 and 314: L L i il L t W 0-9 Table D-4. Summa
Page 315 and 316: -- Lid c i' .- .b) i Internal Distr
Page 317 and 318: It e L L L t u I' f ' ki Federal Ag
Page 319: u 1' 1" Outside Organizations (cont
show all

ORNL-5388 - the Molten Salt Energy Technologies Web Site

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?