Development and Application of COSINE Reactor Monte Carlo Code cosRMC

被引：0
|
作者：
Yu, Hui [1 ,2 ]
Quan, Guoping [1 ,2 ]
Qin, Yao [1 ,2 ]
Yan, Yiman [1 ,2 ]
Chen, Yixue [1 ,2 ]
机构：
[1] State Power Investment Corporation Research Institute, Beijing,102209, China
[2] National Energy Key Laboratory of Nuclear Power Software, Beijing,102209, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2021年 / 42卷 / 03期
关键词：
621 Nuclear Reactors - 914.1 Accidents and Accident Prevention - 922.1 Probability Theory - 922.2 Mathematical Statistics;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
13
引用
收藏
页码：218 / 223
相关论文
共 50 条
  • [21] Development and application of Monte Carlo and COMSOL coupling code for neutronics/thermohydraulics coupled analysis
    Weng, Minghui
    Liu, Shichang
    Liu, Zhenhai
    Qi, Feipeng
    Zhou, Yi
    Chen, Yixue
    ANNALS OF NUCLEAR ENERGY, 2021, 161
  • [22] THERMAL REACTOR BENCHMARK CALCULATIONS WITH THE MCNP MONTE-CARLO CODE
    PRAEL, RE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 846 - 848
  • [23] Criticality qualification of a new Monte Carlo code for reactor core analysis
    Catsaros, N.
    Gaveau, B.
    Jaekel, M.
    Maillard, J.
    Maurel, G.
    Savva, P.
    Silva, J.
    Varvayanni, M.
    Zisis, Th.
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (11-12) : 1689 - 1693
  • [24] Preliminary study on strategy of verification of reactor Monte Carlo code CosMC
    1600, Atomic Energy Press (35):
  • [25] Development and Preliminary Verification of Reactor Shielding Design Code cosSHIELD of COSINE Code Package
    Hu, Ye
    Chen, Yixue
    Zhang, Bin
    Sun, Yeshuai
    Yu, Hui
    INTERNATIONAL YOUTH NUCLEAR CONGRESS 2016, IYNC2016, 2017, 127 : 87 - 95
  • [26] APPLICATION OF MONTE CARLO METHOD IN REACTOR MULTIGROUP CALCULATIONS
    FRANKKAMENETSKI.AD
    JOURNAL OF NUCLEAR ENERGY PARTS A AND B-REACTOR SCIENCE AND TECHNOLOGY, 1964, 18 (10PA): : 591 - &
  • [27] Development and application of variance reduction technique based on response matrix method in the cosRMC code
    Zhang, Xian
    Liu, Shichang
    Zhang, Jingyu
    Chen, Yixue
    ANNALS OF NUCLEAR ENERGY, 2023, 186
  • [28] Development and verification of transport and tally capabilities based on unstructured mesh in Reactor Monte Carlo code RMC
    Li, Jie
    Shen, Pengfei
    Liu, Zhaoyuan
    Li, Qing
    Wang, Kan
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2025, 57 (06)
  • [29] Development of heavy ion transport Monte Carlo code
    Iwase, H
    Kurosawa, T
    Nakamura, T
    Yoshizawa, N
    Funabiki, J
    ADVANCED MONTE CARLO FOR RADIATION PHYSICS, PARTICLE TRANSPORT SIMULATION AND APPLICATIONS, 2001, : 973 - 978
  • [30] The development of a multigroup Monte Carlo code for TRIGA reactors
    Omar, M. R.
    Karim, J. A.
    Yoon, T. L.
    NUCLEAR ENGINEERING AND DESIGN, 2019, 342 : 99 - 114
12345