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  5. A new Monte Crlo cosRMC for PWR and Lead-based fast reactor analysis

A new Monte Crlo cosRMC for PWR and Lead-based fast reactor analysis

来源 :第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) | 被引量 : 0次 | 上传用户：mixiaoya2008
【摘 要】
：
The Monte Carlo method is becoming widely used to do the transport calculation in the reactor physics because of its advantages of dealing with continue energy cross sections and arbitrary geometry.A
【作 者】
：
Xubo Ma Fan Lu Qian Xu Yuan Yao Jiajv Hu Hui Yu 
【机 构】
：
School of Nuclear Science and Engineering,North China Electric Power University,Beijing,102206,China
【出 处】
：
第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)
【发表日期】
：
2016年3期
【关键词】
：
CJS-13 Abstract Template Preparation 
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　　The Monte Carlo method is becoming widely used to do the transport calculation in the reactor physics because of its advantages of dealing with continue energy cross sections and arbitrary geometry.A new reactor Monte Carlo code named cosRMC was developed jointly by the Department of Engineering Physics in Tsinghua University and State Nuclear Power Software Development Center.In previous study,the capability of criticality calculation of cosRMC was verified by using simple critical benchmark,C5G7 benchmark and VENUS-2 3D MOX core benchmark.
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