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核技术, 2016 Some of the next articles are maybe not open access.
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Criticality validation of SuperMC with ICSBEP
Annals of Nuclear Energy, 2016Abstract Monte Carlo transport codes are extensively used in neutronic analysis, especially in criticality safety analysis and shielding analysis. Super Monte Carlo Simulation Program for Nuclear and Radiation Process (SuperMC) is a CAD based Monte Carlo program for integrated simulation of nuclear systems.
Guangyao Sun, Binhang Zhang, Liqin Hu
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Benchmarking of CAD-based SuperMC with ITER benchmark model
Fusion Engineering and Design, 2014Abstract Neutronics design and analysis of fusion reactors is significantly complex mainly on geometry and physical process of neutron. The great challenges brought by advanced nuclear energy system promote the development of Super Monte Carlo Calculation Program for Nuclear and Radiation Process (SuperMC).
Song Jing, Guangyao Sun, Liqin Hu
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SuperMC cloud for nuclear design and safety evaluation
Annals of Nuclear Energy, 2019Abstract For nuclear design and safety evaluation, along with the development of accuracy and efficiency, further demands are proposed for the nuclear simulation to computing platforms, such as convenient large data processing, secured data storage and transfer as well as secured control over the accessing to the codes.
Yican Wu, Lijuan Hao, Liqin Hu
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Neutronic and Safety Analysis of CAREM-25 Small Modular Reactor Using Supermc Advanced Code
2023Zare Ganjaroodi, Saeed +4 more
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Development and testing of a coupled SuperMC and SUBCHANFLOW code for LWR simulations
Annals of Nuclear Energy, 2020Lei Wang, Louhanrong Yu, Yican Wu
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