Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel

Progress in Nuclear Energy - Tập 86 - Trang 1-10 - 2016
Limin Liu1, Dalin Zhang1, Qing Lu2, Kunpeng Wang3, Suizheng Qiu1
1State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
2Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
3Nuclear and Radiation Safety Center, Beijing, 100082, China

Tài liệu tham khảo

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Progress in Nuclear Energy

Tập 86

1-10

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