Study on Minor Actinide Incineration in Molten Salt Reactors with Uranium or Plutonium Loadings.

The paper is concerned with the use of uranium wastes after purification of regenerated fuel from 232U in a molten salt reactor (MSR) in application to minor actinide (MA) burning. The comparison of the uranium and plutonium loadings in an MSR was performed. The results of calculations show that the uranium loading in an MSR is a possible option that has a number of potential advantages: it allows for a higher rate of MA burning during the initial period of MSR operation with approximately the same burnup efficiency and increases the effective fraction of delayed neutrons. The presented calculations are of an approximate nature and first of all show the possibility of effective use of uranium from the waste stream of the enrichment cascade as a fissile material. [ABSTRACT FROM AUTHOR]