Abstract
The lead-bismuth research reactor is one of the most important generation-IV reactors. Currently, Chinese scholars are very enthusiastic about studying lead-bismuth research reactors. Based on the research results in the papers that have been published, research progress on lead-bismuth research reactors in some Chinese research institutes such as the Chinese Academy of Sciences, Shanghai Jiaotong University, the University of Science and Technology of China, and the Insitute of Nuclear and New Energy Technology of Tsinghua University have been conducted. Firstly, Chinese academics attach great importance to the safety analysis of lead-bismuth research reactors in the event of an accident. Besides, CLEAR-I has negative reactivity coefficient feedback, which reflects its safety. The determination of the flow state of the liquid metal will be a prospect for future research. Besides, SMPBN (Small Modular Pb-Bi Cooled Reactor with Nitride Nuclear Fuel) is easy to control during its lifetime and has inherent safety features. China lags behind its international counterparts in MA transmutation. This is also an important prospect in future research. This review is expected to provide a reference for the research of lead-bismuth research reactor.
Highlights
As one of the most important generation-IV reactors, the lead-bismuth research reactor uses leadbismuth alloy as the coolant (Xiong and Yang, 2014)
The determination of the flow state of the liquid metal will be a prospect for future research
Safety analysis has been studied under earthquakes, flow blockage accident, unprotected loss-ofheat-sink, unprotected transient overpower (UTOP), unprotected loss-of-flow, etc
Summary
As one of the most important generation-IV reactors, the lead-bismuth research reactor uses leadbismuth alloy as the coolant (Xiong and Yang, 2014). In 2014, Xiong and Yang of Tsinghua University conducted a physical property study and core design of an accelerator-driven subcritical system cooled by a lead-bismuth alloy with a thermal power of 800 MW and an accelerator proton energy of 600 MeV (Xiong and Yang, 2014). They used a program to study the effects of different griddiameter ratios and the content of minor actinides (MA) on reactivity and burnup processes. The maximum temperature of the coolant pipe surface under accident conditions is 595.0°C, which is still lower than the transient design limit of 650°C
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