Wang Lianjie, Zhao Wenbo, Chen Bingde, Yao Dong, Lu Di. Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients[J]. Nuclear Power Engineering, 2017, 38(5): 145-150. doi: 10.13832/j.jnpe.2017.05.0145
Citation:
|
Wang Lianjie, Zhao Wenbo, Chen Bingde, Yao Dong, Lu Di. Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients[J]. Nuclear Power Engineering, 2017, 38(5): 145-150. doi: 10.13832/j.jnpe.2017.05.0145
|
Wang Lianjie, Zhao Wenbo, Chen Bingde, Yao Dong, Lu Di. Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients[J]. Nuclear Power Engineering, 2017, 38(5): 145-150. doi: 10.13832/j.jnpe.2017.05.0145
Citation:
|
Wang Lianjie, Zhao Wenbo, Chen Bingde, Yao Dong, Lu Di. Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients[J]. Nuclear Power Engineering, 2017, 38(5): 145-150. doi: 10.13832/j.jnpe.2017.05.0145
|
Coupled 3-D Neutronics/Thermal-Hydraulics Analysis for SCWR Core Typical Transients
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Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
- Received Date: 2016-11-01
- Rev Recd Date:
2017-03-21
Available Online:
2025-02-09