Kinetics solution with iteration scheme of history-based neutron source in accelerator driven system

In the time-dependent neutronic analyses of the accelerator driven system (ADS), one of the technical issues is the investigation method of reactor transients for validating why detector responses or fission rates are varied in functions of space and time. In previous studies, numerical analyses for ADS have been conducted by using forward transport methods, focusing on reconstruction of the time behavior. In this study, a source history-based kinetics equation, which is superior to cause analysis of time transients comparing with general forward transport methods, is derived by using the time contributions from each source into responses. For the validation of the applicability, through the re-evaluation of ADS experiment at the Kyoto University Critical Assembly, the time transients of fission rates and detector responses are quantitatively analyzed with the time contributions directly obtained by the proposed method. The expanded analysis ability provided by the proposed method will contribute to investigate the reactor transient of ADS including verification of reactor experiments, analysis of space-time detector responses and establishment of estimation strategy for obtaining the kinetics parameters.