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  5. Study of neutron flux calculation method of irradiation on HFETR

Study of neutron flux calculation method of irradiation on HFETR

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：xuanwuba
【摘 要】
：
The main task for High Flux Engineering Test Reactor(HFETR)is to carry out the irradiation test of nuclear materials,which successfully calls for providing the materials neutron flux within the irradi
【作 者】
：
Lei Zhu Shouhua Sun Jian Li 
【机 构】
：
Nuclear Power Institute of China,Chengdu,610005,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】
：
HFETR Irradiation Neutron flux 
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　　The main task for High Flux Engineering Test Reactor(HFETR)is to carry out the irradiation test of nuclear materials,which successfully calls for providing the materials neutron flux within the irradiation channels accurately,but specified fuel cell geometry and sophisticated in-core loading patterns for HFETR have high requirements on in-core neutronics computation.
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