A software package was developed for coupled thermohydraulic and three-dimensional neutronics calculations of a core in transient regimes of heavy-water reactor installations. This package is necessary for safety validation in regimes with a change in the positions of the control rods or absorber replacement, since strong non-uniformities of the neutron field can arise in these cases. Validation showed that the software package describes the main parameters of a heavy-water reactor installation with sufficient accuracy for engineering calculations and can be used to calculate the dynamics of installations of this type.
机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Zhang, Bin
Li, Qing
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Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Li, Qing
Cai, Yun
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机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Cai, Yun
Liu, Kun
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机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Liu, Kun
Qin, Xue
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机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Qin, Xue
Wang, Shiqian
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机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Wang, Shiqian
Ji, Wenhao
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机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Ji, Wenhao
Guo, Rui
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机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Guo, Rui
Zhao, Chen
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机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Zhao, Chen
Peng, Xingjie
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h-index: 0
机构:
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, ChinaScience and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
Peng, Xingjie
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology,
2022,
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