Is the transmutation of strontium-90 and cesium-137 feasible in a high flux fission reactor

A scheme for a high flux molten salt (plutonium chlorides) fast reactor with a thermal power of 7 GW is presented. It has an internal thermal zone with a liquid target for transmutation of Sr-90 and Cs-137. These fission products are those produced by fast breeder reactors having a combined power of 23 GW and by the fast burner reactor itself with 7 GW. In the case where the power reactors have a breeding gain of G<=0.37 the doubling time for the whole system including the burner reactor is approximately 100 years. With a total neutron flux of 3.8x1016 n/cm2.s and a thermal flux of 2x1016 n/cm2.s, the steady state effective half-life of the Sr-90 and Cs-137 undergoing transmutation is approximately 1.8 years for Sr-90 and approximately 8.9 years for Cs-137. In terms of the hazard coefficient this system gives an improvement by a factor 15. These results indicate that the transmutation of Sr-90 and Cs-137 in a fission reactor, even by using very advanced technologies, may be prohibitive