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Research on the connection calculation of direct kinetics simulation and predictor-corrector Quasi-Static method based on RMC code

•The connection calculation between the weak neutron field and the strong neutron field is implemented in the RMC code.•A connection calculation method between the three-dimensional Direct Kinetics Simulation method and the Predictor-Corrector Quasi-Static method is proposed.•The connection calculat...

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Bibliographic Details
Published in:Annals of nuclear energy 2024-12, Vol.208, p.110797, Article 110797
Main Authors: Jia, Conglong, Wang, Wu, Gou, Yuanhao, Liu, Zhaoyuan, Wang, Kan
Format: Article
Language:English
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Summary:•The connection calculation between the weak neutron field and the strong neutron field is implemented in the RMC code.•A connection calculation method between the three-dimensional Direct Kinetics Simulation method and the Predictor-Corrector Quasi-Static method is proposed.•The connection calculation method is about 3 times faster than the pure Direct Kinetics Simulation method. In the future, it will be used in simulation calculations of reactor start-up without external neutron source. Reactor startup without external neutron source is beneficial to improve the economics of nuclear energy, especially in a more and more competitive energy market with the rapid development and deployment of renewable energy. This paper conducts the research on the connection calculation of Monte Carlo Direct Kinetics Simulation (DKS) method and Predictor-Corrector Quasi-Static (PCQS) method during the weak source start-up process of the reactor based on the Monte Carlo code RMC, addressing the calculation methods for time absorption source, delayed neutron source, reactivity, effective delayed neutron fraction and neutron generation time. It achieves advantages in the calculation efficiency in three-dimensional simulations of the connection calculation between DKS in weak neutron field based on stochastic neutron transport equation and PCQS in strong neutron field based on time-dependent Boltzmann neutron transport equation.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2024.110797