Abstract

Results are presented from calculating the activities of fission products and actinides for the mean fuel burnup of the Belarusian Nuclear Power Plant (Belarusian NPP) (55.6 MW d t–1 U). Rates of the loss of total activity are obtained for the spent nuclear fuel (referred to below as SNF) depending on the period of storage. Calculation studies of the radiotoxicity characteristics of spent WWER-1200 nuclear fuel allows the listing of radionuclides that are potential radiation hazard at different stages of SNF management at the Belarusian NPP. The results are important when making decisions on the environmentally acceptable option for spent nuclear fuel management presented in the Belarusian NPP’s Strategy of SNF Management.

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