1.Institute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, The Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Beijing 100084, China
2.Chinergy Co. ltd, Beijing 100193, China
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Zuo-Yi Zhang, Yu-Jie Dong, Qi Shi, et al. 600 MWe high temperature gas-cooled reactor nuclear power plant HTR-PM600. [J]. Nuclear Science and Techniques 33(8):101(2022)
Zuo-Yi Zhang, Yu-Jie Dong, Qi Shi, et al. 600 MWe high temperature gas-cooled reactor nuclear power plant HTR-PM600. [J]. Nuclear Science and Techniques 33(8):101(2022) DOI： 10.1007/s41365-022-01089-9.
The HTR-PM600 high-temperature gas-cooled reactor nuclear power plant is based on the technology of the high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration project. It utilizes proven HTR-PM reactor and steam generator modules with a thermal power of 250 MW,th, and power generation of approximately 100 MW,e, per module. Six modules in parallel, connected to a steam turbine, form a 600 MW,e, nuclear power plant. In addition, its system configuration in the nuclear island is identical to that of the HTR-PM in which the technical risks are minimized. Under this principle, the HTR-PM600 achieves the same level of inherent safety as the HTR-PM. The concept of a ventilated low-pressure containment (VLPC) is unchanged; however, a large circular VLPC accommodating all six reactor modules is adopted rather than the previous small-cavity-type VLPC, which contains only one module, as defined for the HTR-PM. The layout of the nuclear island and its associated systems refer to single-unit pressurized water reactor (PWR) practices. With this layout, the HTR-PM600 achieves a volume size of the nuclear island that is comparable to a domestic PWR of the same power level. This will be a Generation IV nuclear energy technology that is economically competitive.
High-temperature gas-cooled reactorModuleHTR-PM600Generation IV
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