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

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...

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Bibliographic Details
Main Authors: Nianbiao Deng, Tao Yu, Jinsen Xie, Zhenping Chen, Qin Xie, Pengcheng Zhao, Zijing Liu, Wenjie Zeng
Format: Article
Published: Elsevier 2019-04-01
Series:Nuclear Engineering and Technology
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