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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

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成果类型:
期刊论文
作者:
Deng, Nianbiao;Yu, Tao*;Xie, Jinsen;Chen, Zhenping;Xie, Qin;...
通讯作者:
Yu, Tao
作者机构:
[Liu, Zijing; Xie, Qin; Deng, Nianbiao; Chen, Zhenping; Zeng, Wenjie; Xie, Jinsen; Yu, Tao; Zhao, Pengcheng] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China.
[Liu, Zijing; Xie, Qin; Deng, Nianbiao; Chen, Zhenping; Zeng, Wenjie; Xie, Jinsen; Yu, Tao; Zhao, Pengcheng] Univ South China, Res Ctr Digital Nucl Reactor Engn & Technol Hunan, Hengyang 421001, Hunan, Peoples R China.
通讯机构:
[Yu, Tao] U
Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China.
语种:
英文
关键词:
Th-U fuel;CANDU;Assembly schemes;Core schemes;Time-average model
期刊:
Nuclear Engineering and Technology
ISSN:
1738-5733
年:
2019
卷:
51
期:
2
页码:
377-383
基金类别:
National Natural Science Foundation of ChinaNational Natural Science Foundation of China (NSFC) [11575079, 11605085]; 2018 Graduate Research and Innovation Project of Hunan Province, PR China
机构署名:
本校为第一且通讯机构
院系归属:
核科学技术学院
摘要:
Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant void reactivity of the assembly analyzed in this paper is lower than that of 37-element bundle cell with natural uranium and 37-element bundle cell with mixed TU fuel pins; that the max time-average channel/bundle power of the core meets the limits - less than 6700kW/860 kW; that the fuel conversio...

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