ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site ORNL-4191 - the Molten Salt Energy Technologies Web Site
Work related to the Molten-Salt Breeder Reactor was initiated during this period. Studies were made of the problems related to the removal of the noble gases from the circulating salt to help identify the equipment and systems required to keep the '35Xe poison fraction and the fission product afterheat to an acceptable level. Preparations were begun for operation of a small out-ofpile loop in which a molten salt will be circulated through a graphite fuel cell and for operation of an isothermal MSRE-scale loop with sodium fluoroborate. The major effort of the program at this time is to help establish the feasibility of improved concepts and to define problem areas. Since the production of suitable and reliable salt pumps is one of the longest lead-time items for molten-salt reactors, a major emphasis is being placed on this program. Some of the work related to problems of the Dunlap Scott graphite and other sinks in the MSRR. The sink terms considered are: 1. Decay 2. Eurnup - takes place in the graphite and in the fuel salt passlrig through the core. 3. Migration to graphite - these gases ultimately decay or are burned up. 4. Migration to circulating bubbles ...- these gases are stripped from the fuel loop to go to the off-gas system. Two source terns are considered: generation directly from fission, which is assuined to occur only in the core, and generation from decay of the precursor, which OCCUKS throughout the fuel loop. The model is based on conventional iiiass transfer concepts, Some degree of success has beeil ex- perienced with similar models developed for the MSKE, for example: MSBR but actually performed on the MSRE is 1. Xenon-135 poison fraction calculations. The discussed in the MSRE section of this report. The other work is described below. 7.1 NOBL E-GAS AVlQR Ira THE MSBR R. J. Ked1 In the MSBR conceptual designs, the graphite in the reactor core is unclad and in intimate contact with fuel salt. Noble gases generated by fission and any gaseous compounds can diifuse from the salt into the porous structure of the graphite, where they will serve as heat sources and nuclear poisons. A steady-state analytical model was developed to compute the migration of noble gases to the 90 steady-state model is developed in ORNL-4069. Results of the time-dependent form of the model are summarized in OKNL-TM-1796. 2. A model was developed t~ compute the con- centrations of daughters of very short-lived noble gases in graphite (QRNL-TM-1810). Computed concentrations check very well with measured values. With this model, steady-state l3 5Xe poisoning calculations have been made for the MSBR [556 Mw (thermal) fueled with 233U and moderated with unclad graphite) to show the influence of various design parameters involved. The reactor con- sidered here is essentially that described in ORNL-3996 [P. FZ. Kasten ef a]., Design Studies of 1000-Mw (e) Molten-Salt Breeder Reactors], with specific design parameters as listed in 'Table 7.1.
Table 7.1. Design Parameters -. .... __ ......... ................. . Reactor power, Mw (thermal) 91 Fuel Fuel salt flow rate, ft3/sec Core diameter, ft Core height, ft Volume fuel salt in core, ft3 Volume fuel salt in heat exchanger, ft3 Volume fuel salt in piping between rore and heat exchanger, ft3 Fuel cell cross section ,DOWNFLOW CHANNEL ‘UPFLOW CHANNEL Total graphite surface area exposed to salt, ft2 Mass transfer coefficient to graphite - upflow, ft/hr Mass transfer coefficient to graphite - downstream, ft/hr Mean thermal flux, neutrons sec-’ cm-’ Mean fast flux, neutrons sec-‘ crn-’ Thermal neutron cross section for 233U, barns Fast neutron cross section for 233U, barns Total core volume - graphite and salt, ft3. 233U concentration in core - homogenized, atoms barn-’ Graphite void available to xenon, 75 13’xe parameters Decay constant, l/hr Generation direct from fission, 70 Generation from iodine decay, % Cross section for MSRR neutron spectrum, barns -1 cm 5 56 233u 25.0 8 10 83 83 61 3630 0.72 0.66 5 . 0 1014 ~ 7.6 x 1014 253 3G.5 503 1.11 10 7.53 x 0.32a G.38a 9.94 x los aThe values for the yield of 13’Xe from the fission of 233U are from an old source and were used in the screening calculations. Recent values of 1.11% for generation direct from fission and 6.16% for generation from iodine decay as reported by C. H. Bizham et al. in Trans. Am. Nucl. Soc. 8(1), June 1965, will be user? in the future. The xenon stripping mechanism consists in cir- culating helium bubbles with the fuel salt and then removing them from the system. These bubbles are injected at the inlet to the heat exchanger in the region of the pump. Xenon-135 migrates to the bubbles by conventional mass transfer, and the mass transfer coefficient controls the rate of migration. The circulating bubbles are then stripped from the salt by a pipeline gas separator at the heat exchanger outlet. The heat exchanger, then, is the xenon stripper region of the fuel loop. The principal parameters to be discussed here will be: 1. Diffusion coefficient of xenon in graphite. 2. Parameters associated with circulating bubbles. (a) Mass transfer coefficient to the bubbles. (b) The surface area of the bubbles. 3. The surface area of graphite exposed to salt in the core. In the plots that follow, the diffusion coefficient of xenon in graphite at 120Q°F with units of ft2/hr
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Table 7.1. Design Parameters<br />
-. .... __ ......... ................. .<br />
Reactor power, Mw (<strong>the</strong>rmal)<br />
91<br />
Fuel<br />
Fuel salt flow rate, ft3/sec<br />
Core diameter, ft<br />
Core height, ft<br />
Volume fuel salt in core, ft3<br />
Volume fuel salt in heat exchanger, ft3<br />
Volume fuel salt in piping between rore and heat exchanger, ft3<br />
Fuel cell cross section<br />
,DOWNFLOW CHANNEL<br />
‘UPFLOW CHANNEL<br />
Total graphite surface area exposed to salt, ft2<br />
Mass transfer coefficient to graphite - upflow, ft/hr<br />
Mass transfer coefficient to graphite - downstream, ft/hr<br />
Mean <strong>the</strong>rmal flux, neutrons sec-’ cm-’<br />
Mean fast flux, neutrons sec-‘ crn-’<br />
Thermal neutron cross section for 233U, barns<br />
Fast neutron cross section for 233U, barns<br />
Total core volume - graphite and salt, ft3.<br />
233U concentration in core - homogenized, atoms barn-’<br />
Graphite void available to xenon, 75<br />
13’xe parameters<br />
Decay constant, l/hr<br />
Generation direct from fission, 70<br />
Generation from iodine decay, %<br />
Cross section for MSRR neutron spectrum, barns<br />
-1<br />
cm<br />
5 56<br />
233u<br />
25.0<br />
8<br />
10<br />
83<br />
83<br />
61<br />
3630<br />
0.72<br />
0.66<br />
5 . 0 1014 ~<br />
7.6 x 1014<br />
253<br />
3G.5<br />
503<br />
1.11<br />
10<br />
7.53 x<br />
0.32a<br />
G.38a<br />
9.94 x los<br />
aThe values for <strong>the</strong> yield of 13’Xe from <strong>the</strong> fission of 233U are from an old<br />
source and were used in <strong>the</strong> screening calculations. Recent values of 1.11% for<br />
generation direct from fission and 6.16% for generation from iodine decay as reported<br />
by C. H. Bizham et al. in Trans. Am. Nucl. Soc. 8(1), June 1965, will be user? in <strong>the</strong><br />
future.<br />
The xenon stripping mechanism consists in cir-<br />
culating helium bubbles with <strong>the</strong> fuel salt and <strong>the</strong>n<br />
removing <strong>the</strong>m from <strong>the</strong> system. These bubbles<br />
are injected at <strong>the</strong> inlet to <strong>the</strong> heat exchanger in<br />
<strong>the</strong> region of <strong>the</strong> pump. Xenon-135 migrates to <strong>the</strong><br />
bubbles by conventional mass transfer, and <strong>the</strong><br />
mass transfer coefficient controls <strong>the</strong> rate of<br />
migration. The circulating bubbles are <strong>the</strong>n<br />
stripped from <strong>the</strong> salt by a pipeline gas separator<br />
at <strong>the</strong> heat exchanger outlet. The heat exchanger,<br />
<strong>the</strong>n, is <strong>the</strong> xenon stripper region of <strong>the</strong> fuel loop.<br />
The principal parameters to be discussed here<br />
will be:<br />
1. Diffusion coefficient of xenon in graphite.<br />
2. Parameters associated with circulating bubbles.<br />
(a) Mass transfer coefficient to <strong>the</strong> bubbles.<br />
(b) The surface area of <strong>the</strong> bubbles.<br />
3. The surface area of graphite exposed to salt in<br />
<strong>the</strong> core.<br />
In <strong>the</strong> plots that follow, <strong>the</strong> diffusion coefficient<br />
of xenon in graphite at 120Q°F with units of ft2/hr