Precise information of the variation of fission product concentration for time after a fission burst is necessary for safety designs and operations of nuclear power reactors, fuel storage, transport flasks, and for spent fuel management and processing. In this study, an efficient computation procedure has been introduced for exact analysis of the buildup and decay of fission products for time following a fission burst. The analytical data of fission product concentrations was applied to calculate aggregate fission product decay heat from neutron fission of 235U, 238U, 239Pu and 232Th.
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