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المؤلفون: Guanbo Wang, Shichang Liu, Gaochen Wu, Jingang Liang, Kan Wang
المصدر: Annals of Nuclear Energy. 85:830-836
مصطلحات موضوعية: Nuclear physics, Neutron transport, Complex geometry, Nuclear Energy and Engineering, Monte carlo code, Computer science, Nuclear engineering, Monte Carlo method, Neutron, Research reactor, Deterministic method, Burnup