600 MW<sub>e</sub> high temperature gas-cooled reactor nuclear power plant HTR-PM600

Zuo-Yi Zhang; Yu-Jie Dong; Qi Shi; Fu Li; Hai-Tao Wang

doi:10.1007/s41365-022-01089-9

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600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2022-09-26

- 600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600
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- 600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600
- Nuclear Science and Techniques 2022年33卷第8期文章编号：101
- Affiliations：
  
  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
- Author bio：
  
  *wanght@tsinghua.edu.cn
- Funds：
  
  Chinese National S&T Major Project(ZX069)
- DOI：10.1007/s41365-022-01089-9
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Zuo-Yi Zhang, Yu-Jie Dong, Qi Shi, 等. 600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600[J]. Nuclear Science and Techniques, 2022,33(8):101

Zuo-Yi Zhang, Yu-Jie Dong, Qi Shi, et al. 600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600[J]. Nuclear Science and Techniques, 2022,33(8):101
Zuo-Yi Zhang, Yu-Jie Dong, Qi Shi, 等. 600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600[J]. Nuclear Science and Techniques, 2022,33(8):101 DOI： 10.1007/s41365-022-01089-9.

Zuo-Yi Zhang, Yu-Jie Dong, Qi Shi, et al. 600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600[J]. Nuclear Science and Techniques, 2022,33(8):101 DOI： 10.1007/s41365-022-01089-9.

摘要

Abstract

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.

关键词

Keywords

High-temperature gas-cooled reactorModuleHTR-PM600Generation IV

references

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600 MWe high temperature gas-cooled reactor nuclear power plant HTR-PM600

600 MWe high temperature gas-cooled reactor nuclear power plant HTR-PM600

DOI：10.1007/s41365-022-01089-9

摘要

Abstract

关键词

Keywords

references

600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600

600 MW_e high temperature gas-cooled reactor nuclear power plant HTR-PM600