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AbstractAbstract
[en] The solidified fuel salt and flush salt from the Molten Salt Reactor Experiment (MSRE) have been stored at the Oak Ridge National Laboratory (ORNL) since the reactor was shut down in 1969. The fluoride salt eutectic, containing 37 kg of uranium plus plutonium and fission products, is safely contained in three heavy-walled Hastelloy tanks, which are located inside a reinforced concrete cell. Removal of these salts to a remote location is not feasible until an appropriate repository has been identified, built, and placed in operation. Since this may take many years, extended storage-in-place was critically evaluated. The evaluation, which involved a preliminary assessment of several options for enhancing the integrity of in-place storage, including containment improvements, the addition of chemical getters and neutron poisons, and entombment in concrete, showed that this approach was a rational and safe solution to the problem for the short term. Entombment is essentially nonreversible, but the other options are open-ended; they do not limit the future selection of a final disposal option. Specific actions and improvements that would enhance safe containment during extended storage and would also be of future benefit, regardless of which disposal option is finally selected, were identified. 20 refs., 5 figs., 22 tabs
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Sep 1985; 135 p; Available from NTIS, PC A07/MF A01; 1 as DE86001720
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