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Nationa' Technical Infernsation Service U S Bepasment of Camrnerce
5285 Part Royal Raaa, Springfield, Virginia 22151 Printed Copy $3 00. Microfiche $0.95 Price
This report was prepared as an account of work sponsored by the Uni ted States Goverlment. Neither the United States nor the United States Aromic Energy Commrssion, nor any of their employees, nor any of their contractors, subcontractors, or their emp'eyees, makes any warranty. express or implied. or assumes any legal Irabdity or respansibrlity far the accuracy, completeness OF
usefulness of any ivforrnatmn, apparatus. product OF process disclosed, or represents that i t s use would net infringe privately owned rights
ORNL-4812 UC-80 - R e a c t o r Technology
MOLTEM-SALT REACTOR PROGUN
THE DEVELOPMENT STATUS OF MQLTEM-SALT BREEDER REACTORS
XiI. W. Rosenthal, Program D i r e c t o r P. N. Haubenreich, Associate Direc tor R. B. Briggs, Associa te Di rec tor
August: 1972
OAK RIDGE KATIQNAL LABOMTOKY Oak Ridge, Tennessee 37830
o p e r a t e d by U N I O N CARBIDE CORPORATION
f o r the E.S . ATOMIC mmeY COXMISSION
..... .....y ....&
.... i...... ..<d
.... L.X.II
ABSTRACT
Molten-salt reactor technology, under development since 1947,
A connected
The
has led t o a concept of a high-temperature, thermal-neutron breeder reactor that operates on the t h o ~ i u m - ~ ~ ~ U fuel cycle. processing plant that continuously removes protactinium and fission products from the fuel salt is a bas ic feature of the system. success of the Molten-Salt Reactor Experiment that was operated be- tween 1965 and 1969, the development of a new processing method that allowed simplification of the breeder design, and the potential breed- ing performance, economfcs, and safety of the concept, are cited i - n this report as arguments for the continued development of MSBR's. The report reviews the status of the technology, identifies further development needs f o r an MSBR, and gives the program staff's assess- ments of the uncertainties and the likelihood of success. Separate. chapters are devoted t o reactor physics, chemistry, graphite, reactor metals, reactor eomponents and systems, ce l l s and building, control and instrumentation, fuel processing, maintenance, design studies, and environmental effects and safety.
Keywords: review, molten salts, reactors, breeding, development, design, maintenance, safety, chemistry, processing, a l l o y s , graphite.
CONTENTS
....
..... ,.. . . . &%*
Chapter Page
1. INTRODUCTION, S W R Y , A m CONCLUSIONS . * 0 . . a 0 D . * * h Backgroun$ . . . . . . . . . . . . . . . . . . . . . . . . . 2 Features of t he Single-Pluid Breeder Reactor . . . 4 The Processing Plan t FOP the Single-Fluid Breeder . a 6 Nuclear and Economic Performance of the Breeder . e . . 6 The Status of Development, the f i j o r Uncertainties, and the Alternatives . . - . . . . a e . . . a . e e 8
~eactor ~hysfcs ana F ~ ~ I cycles e a e e . a . a a 8 Fuel and Cookant Chemistry . a . . e . 8 Graphite .. e - . e e * . . * . . * . e * . . 9 Materials f o r Salt-Containing Vessels and Piping e . . 10 Reactor Components and Systems . . . . e e e 12 Cells , Bui ld ings , and Containment e e a a e a . a I e 14 Instrumentation and Controls . . e e . . . e . e . e I 4 Fuel Processing . . e e . e . e a . e . 15 Maintenance . . e . . . e . e e e . e 17 Design Studies and Capital Cost Estimates . . e e 1 7 Environmental Effects and Safety a e e . e . a e e e 18
Future Development Program e . e . . . - e a . a e 1 9 The Incentives for MSBR Development . . e e . a e 2 1
Fuel Utilization . e . e a . e a e e e e a e a . a 22 P o w e r C o s t e e . e e . e * a . e n 0 . e 0 0 . . e . 22 Safety * 0 . a a e . . a * * e e e s a e m * e . * 0 * 25
m e Likeiifaooa sf success . e e . . a . . . a 26 Fuel Utilization . . . . e e . a a e a . 27 Powerrcost * * . e e a . e 0 . s 0 0 . D 0 . . 0 D * 27 Safety s . . 0 a . s 0 . e . e 0 * 0 . . . e * e rn 28
Overall Conclusions . . . . . - e a e a . e . a a 38 References f o r Chapter li . . . e . . e e e . . . . e e 31
2. EVOLUTION AND DEVELOPPENT OF NOLTEN-SALT Origins . . a e . - C . O s . . s 0 . .
Rela t ion tu Other Fluid-Fuel Programs . Early MSBR Concepts . . . . e e e a
T h e M S R E . * . . * . . o . e * . . a
Description e . a . e a . . e e . Development and Construction e . e
Operation e . e 0 . . . 0 . . . m . . Results...... - .
Recent M~lten-Salt Reactor Concepts a . Current Programs I . . . e . - . . e
USAEC PloHten-Salt Reactor Programs . Industrial Studies . . . . Foreign Programs . e e . s e * e e
References f o r Chapter 3 . . . . e . .
P u r p o s e . * . . - . e
REACTORS . . e . 3 3 r . . . * * . . * * 33 . . 0 * . . . . . 0 34 . . L O . . * . . . 3% e . . . * e . s . . 35 0 0 . . . . . . 0 0 35 . . . * . . . e 0 0 36 . . * . . . a , . . 36 . s o e . . . e o . 48 . s . . . s * . . * 41 m . . a . . . * . . 4 2 e . . * . . . * * . 45 * * . . . D * . . . 45 * e . . . . a . . * 46 0 . . * * 0 * 1 e . 46 m . * . e . . r a . 48
Chapter
. . ..........
Page
3. DESIGK CONCEPT OF THE SINGLE-FLUID MSBR 0 . omh, Reference Design * * 0 . m 0 . * 0
Objec t ives D I e s I . s 0 * e 0 e e 0
O r e Csnservatisn * 0 0 . . 0 . * 0 0 . P s w e r C o s t . a . e e e * D * e * e
S a f e t y and Environmental Cons idera t ions Technical F e a s i b i l i t y * D s a s D . e D
General e ~ ~ ~ ~ e p t s f t h e s i n g i e - n u i a weeder Features of the Referenee Design e I
Alternatives t o t h e Reference Design e . . a
Ebasco Variat ions f rom QRXL Design e e e
Low-Power-Density Core e e . e a
References f o r Chapter 3 a e e e e a e e e
..... ,..... v.-
........: ,.... ...... 1-
vi
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Chapter Page
5. (cont.)
Fission Product. Behavior . e a . . . . a e . e . e . a . 116 General.. . a s . . . e . - . a a 116 Major Groups and Y i e l d s . e e . e e e e . e e . . a 1 1 7
S a l t S a m p l e s . . - . . . * . . . e - . a E22 Deposition e . a . . I . e . e e . e . e . 1 2 2 G a s S a m p l e s . . ~ . . . ~ . . . . . . . f . O ~ . . ~ 125
Nob leMeta l s e . a . . a . = e e e e . . e . 125 Salt-Borne . . a e . e . a e a . . a . 1125 Niobium . * . - * . . e * . . a e * . . . e a . - - 1 2 9 Gas-Borne . e a . e . . . . . a a . a . = 129 Deposition on Graphite and Hastelloy N e . e . * . 138
Iodine O . . O ~ . . . . . D . . . O O . . L ~ . . . s . 133 EvaLrnation . a I a . a a e e . e e a . e . . . e 133 Futurework a . e . a a . . e . e . e e 135
Coolant Salts . . . e e e e e . . . . . 135 Basis f o r Choice of Composition . e e e . . a a - . 135 Present Status of FHuoroborate Chemistry a . a . a 137
Phase Behavior - . . I . a = a I . a a e e e I 137 Behavior w i t h Hydroxide Ion e . e a e . . e 139 Physical Properties . . . e . . a e e e 139 Compatibility w i t h Hastelloy N e e . a a . a . . 141 Interactions with Steam . . . . . - . . . e a 142 Interactions with Fuel S a l t e e . a e . a e . - a 1 4 2 Purification of Fluoroborate Mixtures . e e e e . . 144 Radiation and Stability e . . . - . . . . e 145
Evaluation and Summary of Needed Work e . . e . a 145 Analytical Chemistry e a . . a . a . e e . e a 146
Requirements . e . a . e . e . . a e . a 146 Experience . * . . e e a . e . . . . e e 1 4 7
Sampling * . . s D . * - D . . * a * . . f - s e s . * 148 Oxide r D . . P . . . . . . . . . l O . . r D . . . s 148 Uranium a e # . - . . . - . . * . * . . . e * . E49 u3-t . . s . . . . . . . . . . . . . . . . . s * s e a a49 Spectrophotometry of Radioactive Samples e a e . 1 4 3 GasAnalysis . . . . . . . . . . . . . . . . . . 152 Gama Spectrometry at the MSE!E e . e e e a e . e e 152 Bismuth . . e e * . * . a * . . * . - - * . e - e 152
Current Research and Development e . . . e . e . . . . . E52 Electrochemical Research . . . e . . - a . a . e 153 Spectrophotometric Research . . . . e . . . e 1 5 9 Transpiration and Gas Analysis . . e . . . . a 1 6 1 Pn-Efne Applications . . . . . . e . e . e . e . 163
P u t u r e W o r k . . . . . . . . . . . . . . . . . . . . . . . 165 Evaluation 166
Stable Salt-Soluble P l u o r ~ i d e s . a . . a - . a . e . 122
References for Chapter 5 s 0 0 . 0 0 . . D 0 . . s s . e . 1 6 7
Vii
22% 222 222 222 226 226
.... .x.
Chapter Page
8. (cont . ) . . ,.... ,&
.... ._. .% _a
.... *.:s
..... .a,*
.... .... ........ .... >
Pump Experience e e . e . . e e . . . e . a e . Short-Shaft Bump . . . . . . . a . e a e a . Long-Shaft Pump . . . . e . . e . . e e
I n d u s t r i a l Experience and I n t e r e s t . . . . e e
S t a t u s of Pump Technology . . = e . e . . . e a e . . Sca l ing up Pump Capaci ty , . . e e . . . . e e
F a b r i c a t i o n . e . . a . . a a . . . . - Long-Shaft Pump . . . . a e . a a . I e . a
P o t e n t i a l Improvements . . a . . . . a . e
I n d u s t r i a l Involvement . . . . e . I . e a e
E f f e c t s of U n c e r t a i n t i e s . . . . a . e . . e
S a l t Pump Development Requirements a . e . e . a e . Evalua t ion . . O . . . . . O a . . O O . . e . O .
Coolant System e e . a a . . a . . e . . e . e . . D e s c r i p t i s n . . . . . . . . . . . . . . . . . . . . . . a
Experience wi th Coolant Sal ts . . . . . . a e a
S t a t u s s f F lus robora t e Coolant Technology . e . e a . U n c e r t a i n t i e s i n Use of F luorobora te a e e . e . a e
Fur the r Development Work . e . . e e a . a e . . a
D e s i . . . . . . . . . . . . . . . . . . . . . . . . .
Cover G a s Addit ion t o and Removal from
Corrosion Product Deposi t ion e . e . . . e . . e e . a
Mist Control . e e . a . . . a . . . . e e
C o o l a n t L e a h a a e a . . . . . . . e . . Evalua t ion a . . e . e a a . . e . . . e e .
Heat Exchangers a e . e . e . e . e a . . . e . . e . Requirements and Criteria f o r the Brimary Heat
Exchangers and S t e a m Generator . e e . . a e . . Current Concepts . . . . . e e . . . e . . Heat Trans fe r Experience . . e . . e e . . e . . S t a t u s of Heat Exchanger Technology e . . . . . . . a
U n c e r t a i n t i e s and Thei r S e n s i t i v i t y t o Nonachievement of Objec t ives . . . . e . . a . . . e .
Feedwater Temperature L i s t e . . - . . . a . e . . . a
Tube Sheet P r o t e c t i o n . . e . . . . a - . . a . Flow I n s t a b i l i t i e s i n t h e S t e a m Generator e . e a . Conf igura t ion . e . . e . . e e e . . . a . . Pressure Ful se from Rupture of a Steam Tube e . . . Cor re l a t ions and Phys ica l P r o p e r t i e s . . a . . . a . Thermal Trans i en t s . . . . . . . . . . . e a . e . S t e a m Wastage and Leak Detec t ion
( S t e ~ i ~ Generator) . . a . . . . a . . . . F i s s i o n Product Deposi t ion e . . . e . e e e e e
Materials Compat ib i l i ty e . . a . e . . . . e
F a b r i c a t i o n Techniques . e . . e e . e e .
t h e P u m p B o w l . . * 0 0 . m * 0 0 * * D . . . e . e
on-Line Analysis . . . 0 . . . . . a . e . s . s D D
Materials Experience * . . a 0 . . * e e . e . . * s . .
229 2 2 3 2 31 2 33. 2 31 232 2 32 233 233 233 2 3 3 2 34 2 34 2 35 236, 236 237 233 242 2 4 3
243 2 4 3 244 244 244 245 245
245 247 25Q 250 2 5 1
252 252 2 5 3 253 253 253 254 2 54
254 254 254 255
... .... i ...... I ._
ix
Chapter
8. (cant.)
255 255 255 256 257 257 257
259 260 268 261 262 262 262
26 3 263 264 2 64 264 265 265 265 265 266 267 268 268 268 269 269 269 270 230 231 271 2 7 3 233 2 7 3 273 2 34 2 74 276 276
282 284 286
282
..... c..
Chapter
8. (cont.)
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MSWGasSystems e . -
DeSCriptiOn . . 0 . . . . s . . . . . . 0 . . e e . 6
Analysis of Noble Gas Stripping . e e . a . e . O f f - G a s System Performance . . . * . . . . e
Development Studies . . . . a e e . . Effects of Unknowns and Uncertainties . . e e e . . . e e
Future Work e . * e . * . 0 e e 6 . . I . * * - . e . Overall Evaluation e a . . a . e . . . I .
Summary . . ~ . . O . . . . e . O . . O O . . . ~ * ~ . ~ ~
References f o r Chapter 8 . . . . e . . e e . e . . e a a . e
9. CELLS, BUILDINGS, AF3B CONTAINMENT . - e a . . . a . . e
Requirements e . a a a . . . e . a e . e e . . MSKE . . . . . s . . . . I . . . O e . . . . * ~ ~ . ~ *
MSBRBuilding. * . e * . * . a e . . e e e * .
M S B R C e P l s 0 . e . s . 0 . . * - 0 . e . e D D . * 0 0 .
De§CriptiQn a e . . . . e . e . . a . . . a a e e
Status and Uncertainties . . a a . e . . e e e e . . Evaluation . . e e . e . . e a . . e . . . .
10. PLANT CONTROL AND ENSTKUMENTATXON e e . . . e a e . Requirements and Current Concepts . . . . e . e e . . e
Systems f o r N o r m a l Operation e . . . e . . e e a
Emergency Systems . . e . . . - e . a . e - . . a e
Features Peculiar to XSBR e e e . . a . . e e . a
Experience with the MSRE: and Other Facilities a . * e . e
In§trUlTl@lltatiQn e . . . a e . e a e . . . . . e e
Control Analyses 0 . . I * * . * a . . 0 D . . s * * . . * D
Computer Models . 0 . 0 0 * . . e * I . . . D * e . e
Analysis of Steady-State Conditions . e . e . . e a . Analysis of Transient Behavior e . . . . . . Accident Analyses . . . . . . . . a . . . . e e . Reactivity Control . . e . a . . . a . . e . . . . . a
Instrumentation . . . t . . . D 0 . s e . e . . * m 0 . . High-Temperature Flux Sensors . a . . e a e . . *
Process Instrumentation 0 . . . . . 0 . . . s e a . a 6
Rod Drives . . . * . . e * . a * . . - - . . e e
Salt Throttling Valves . . . - a . . . e e e e . . a
Digital Computer Application f o r Control and
Chemical Plan t Instrumentation and Control . . e . Uncertainties and Alternatives . . e e e . e . . . . e
Evaluation . . . . . e e . . . . . . . . . . * . . . References f o r Chapter 16 . . . . . . . . e . . . e e
BataHandling * e . e . . * . . * 0 . e 6 0 * 0 . .
2 86 2 86 287 288 290 294 296 297 29 7 300
309 309 309 309 310 411 3 1 2 313
315 315 3 15 316 316 317 318 320 321 321 322 3 2 3 32 3 324 324 324 325 325
326 326 326 328 329
xi
Page
331 a 31
333 335 439 339 34 3 346 34 7 34 7 349 35 0 35 l 35 E 35 2 353 354 35 6 35 6 35 3 35 8 35 8 359 3.59 35 9
360 36 1 362
12 . rn1NTEP;rnCE a * P 0 . e e a
concept s a . 6 0 . * 0 0
Technologica l Background EISE P r e p a r a t i o n s 0 D . a
Extent of MSW Experience ConePusions f rom Pzsa " 0
Reference Des ign MSBR - * 0
Containment a 0 * * e e
A f t e r h e a t . 0 e 0 a . G r a p h i t e Replacement e a
S t a t u s , e a e e a = - Fur ther Work m 0 D . . e 0 0
E v a l u a t i o n . = . . References f o r Chapter 1 2 0
r,
k.,
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.... ..... x.9
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13. DESIGN STUDIES Ab919 CAPITAL COST ESTIMATES - I n t r o d u c t i o n e e . a e . . . e . . Primary Systems Layout and S t r u c t u r a l Design
Background and S t a t u s . e . e e . a
S e n s i t i v i t y t o U n c e r t a i n t i e s a e e e
Future Work e e e e a . e . . e . Eva lua t ion . a e e . e . .
Design Methods - Cudes and Standards a . e
Background . = e e e e e
S t a t u s e a 0 0 a a 0 . m D 0 . r s
S e n s i t i v i t y t o U n c e r t a i n t i e s e . F u t u r s Work * . . . e e e . e e
Evalua t ion . e . + . e . a
C a p i t a l Costs . a . e e . a
Background and S t a t u s a . . S e n s i t i v i t y t o U n c e r t a i n t i e s a e . Eva lua t iun = . e e . e a e
Conclusions - . a . e e e e e
References f o r Chapter 2.3 a e e e e e a
. . 0 . . 0 . . 379 e 0 0 . 0 0 . . 379 . e . . . e . * 379 * . . . , D . . L 379 . . . e . e e . 380 . D e . . e e . 381 * . * * e . . * 381 0 0 e . a . m . 381 . . * * . . e 0 38% . . . . e * . . 38% . e * . . * * . 382 - . . D O . . * 383 a . . e . . . # 384 . * * . . * 0 . 384 . . . . e . . . 384 0 * . . 0 * . . 385 e * a o e . e o 386 . * 0 0 * . 0 e 386 * * . . D O . . 387
14 . ENVIRONPENTAL EFFECTS AND SAFETY e e . . e a a . a e 389 General Considera t ions a e . a a . . . * . e e e e - 389 C h a r a c t e r i s t i c s of Reference-Design MSBR . . e e . a . 390
Environmental E f f e c t s of Normal Operation e e . e - e e 390 Nuclear S a f e t y e e e a e e a e . e e 391 Radionuclide Decay Heat ing . a e e a a a a a . 395 I n t e r a c t i o n of Materials e . . e . a . e . 399
Coolant S a l t Hn te rac t ions . . e a . e a e a 400 Engineered S a f e t y Fea tu res . a . e e . a . e e 402 S i t i n g Cons idera t ions . . . . . . a e . 403
T r a n s p o r t a t i o n During C o n s t r u c t i ~ n . e e . e . a 404 T r a n s p o r t a t i o n During O p e r a t i o n . . . e a . - a . 404 E f f l u e n t s e . * . e . . e . . * . . * . 406 Radionuclide Inventory . . . . e . e . e . . e I . 406 Design-Basis Accident . e . . e e . . . a a . a e 406 Decommissioning . . . . . e . . e e . . . . . . 406 Summary . - . . . . . . . . . a e a . e a 408
Experience and Knowledge e . . . e . . . . . e . e e 408 Containment . . . e a . . a e . e a e . . . . 408 Ins t rumen ta t ion and Cont ro l . e . . . . e . e e 489 S a l t Handling . . e . . . e . . . e . . . . e e 409 Uranium Behavior . . . . e e . . + e e . e e . 409 Fission-Product Behavior . . . . . . e a . 418 K i n e t i c Behavior . . . e . . . e . . . . a . . e 411
F u r t h e r w o r k . a e . . . a . . . . . . e . . . - a . 4 l E E v a l u a t i o n . . . . . . . . * . . . . * * . . . * . . . - . . 415 References f o r Chapter 1 4 . e . e e e e . . . * - . 416
COrrQSiOn . . ~ O D . . O O . . . . . . . . . O . ~ ~ 399
X i i i