MCS – A Monte Carlo particle transport code for large-scale power reactor analysis

DC Field Value Language Lee, Hyunsuk ko Kim, Wonkyeong ko Zhang, Peng ko Lemaire, Matthieu ko Khassenov, Azamat ko Yu, Jiankai ko Jo, Yunki ko Park, Jinsu ko Lee, Deokjung ko 2020-02-27T12:33:02Z - 2020-02-20 ko 2020-05 ko
dc.identifier.citation ANNALS OF NUCLEAR ENERGY, v.139, pp.107276 ko
dc.identifier.issn 0306-4549 ko
dc.identifier.uri -
dc.description.abstract A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan National Institute of Science and Technology (UNIST) with the aim of performing the high-fidelity multi-physics simulation of large-scale power reactors, especially pressurized water reactors (PWR). The high-fidelity multi-physics analysis of large-scale PWR is a challenging problem due to two aspects, the first being the difficulty of implementing various state of the art techniques into a single code system, and the other making it feasible to run such simulations on practical computing machines within reasonable amount of memory usage and computing time. In this paper, features implemented into MCS for large-scale PWR simulations are described including but not limited to depletion, thermal/hydraulics coupling, fuel performance coupling, equilibrium xenon, on-the-fly neutron cross-section Doppler broadening, and critical boron search. The efficient memory usage for burnup simulation and the high performance of MCS through various algorithms and optimizations (parallel fission bank, hash indexing) are illustrated on Monte Carlo performance benchmarks. Finally, the large-scale PWR analysis capability is fully demonstrated with BEAVRS Cycles 1 & 2 calculations. ko
dc.language 영어 ko
dc.publisher Elsevier Ltd ko
dc.title MCS – A Monte Carlo particle transport code for large-scale power reactor analysis ko
dc.type ARTICLE ko
dc.identifier.scopusid 2-s2.0-85077231931 ko
dc.type.rims ART ko
dc.identifier.doi 10.1016/j.anucene.2019.107276 ko
dc.identifier.url ko
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