600-MW_(e)high-temperature gas-cooled reactor nuclear power plant HTR-PM600

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

作者机构：Institute of Nuclear and New Energy Technology of Tsinghua UniversityCollaborative Innovation Center of Advanced Nuclear Energy TechnologyThe Key Laboratory of Advanced Reactor Engineering and SafetyMinistry of EducationBeijing 100084China Chinergy Co.LtdBeijing 100193China 

出 版 物：《Nuclear Science and Techniques》 (核技术（英文）)

年 卷 期：2022年第33卷第8期

页      面：69-76页

核心收录：

学科分类：080802[工学-电力系统及其自动化] 0808[工学-电气工程] 08[工学] 

基　　金：supported by the National S&T Major Project (No.ZX069) 

主　　题：High-temperature gas-cooled reactor Module HTR-PM600 GenerationⅣ 

摘      要：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 *** 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 *** modules in parallel,connected to a steam turbine,form a 600-MW_(e)nuclear power *** addition,its system configuration in the nuclear island is identical to that of the HTR-PM in which the technical risks are *** this principle,the HTR-PM600 achieves the same level of inherent safety as the *** concept of a ventilated lowpressure 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 *** layout of the nuclear island and its associated systems refer to single-unit pressurized water reactor(PWR)*** this layout,the HTR-PM600achieves a volume size of the nuclear island that is comparable to a domestic PWR of the same power *** will be a GenerationⅣnuclear energy technology that is economically competitive.