Study on the Framework of Fission Product Source Term for Nuclear Power Plants

Abstract

The problems occurring in the fission product source term calculations for M310/CPR1000, EPR and AP1000 are briefly analyzed, based on the related regulations and standards, as well as operational feedback, review experiences and recent research achievements for nuclear power plants in China. The framework of fission product source term proper to China has been first studied and proposed in perspective of the purpose of source terms. The calculation processes of fission product source term are rearranged and the requirements for deferent reactor types are specified. The proposed framework can be taken as a foundation for solution of the long-standing problems in the calculation of fission product source term and provide reference for source term calculation.

Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance

“…Yang et al [8] introduced the analysis method, scope, and main operating procedures of the source items following the Qinshan Nuclear Power Plant accident and calculated the release, migration, and distribution of nuclides under the design-basis accident through the accident analysis program. Liu et al [9] analyzed the problems in the calculation of the fission product source term of M310/CPR1000, EPR, and AP1000 and modified the calculation process of the fission product source term. Jin et al [10] used the modular accident analysis program-integrated severe accident analysis code (MAAP-ISAAC) to quantitatively evaluate the amount of radionuclides released into the environment following an interfacing system loss-of-coolant accident.…”