The Preliminary Analysis Of Transmutation Characteristics Of Long-life High Level Radioactive Waste In Sodium-Cooled Fast Reactor

As the rapid development of nuclear power, the spent fuel of TRU, and especially the minor actinides, will be the potential radioactive hazard in a long term.Our country's nuclear power plants start late,but because of the sharp speed,we still encounter the problem of the cumulativity of MA.Fast reactor has been known the most efficient and feasible transmute system.Transmutation of MA in fast reactor also can be used to produce enegy.This paper study the neutronics of MA transmutation in fast reactor.First, we choose a beachmark to confirm that the calculation of NEWT code is feasible in fast reactor assembly, which is base on the 2-D discrete ordinate method.Then, the paper choose the model of CEFR as the reference model, to research the characteristics of transmutation on MA,and obtain the effects on Keff and fuel temperature coefficient with different actinide nuclides.They will be large effect on some parameters with the addition of MA.So, the quatities of MA in assembly will be paid enough attention.As the above, the paper choose CDFR core model to have a further study, establishing a full reactor core with 3-D Monte Carl code KENO-VI,and studying its neutronics characteristics, such as effective multiplication factor, fuel temperature coefficient, sodium void coefficient, controller pin value, and so on.The results indicate that, the parameters in different position have large diffenences, it must be designed differently in different regions.