高温气冷堆氦气透平压气机和主氦风机研究进展  

Helium turbo-compressor and circulator for a high temperature gas-cooled reactor

作　　者：王捷[1] 王宏[1] 赵钢[1] 杨小勇[1] 叶萍[1] 曲新鹤 WANG Jie;WANG Hong;ZHAO Gang;YANG Xiaoyong;YE Ping;QU Xinhe(Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China)

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《清华大学学报（自然科学版）》2021年第4期350-360,共11页Journal of Tsinghua University(Science and Technology)

基　　金：国家“八六三”高技术项目(2005AA511010);国家科技重大专项资助项目(ZX06901);中核集团青年英才项目。

摘　　要：具有固有安全特性的模块式高温气冷堆(high temperature gas-cooled reactor,HTGR)具有反应堆出口温度高的特点,可与闭式Brayton循环或Rankine循环耦合,实现高效率的发电。氦气透平压气机和主氦风机分别是与这2种循环耦合的高温气冷堆系统中的关键动力部件,该文针对氦气闭式Brayton循环,分别从稳态与动态特性2个方面揭示其内部循环机理;同时针对循环内核心部件氦气透平压气机,开展2.2 MW样机研制与120 MW商用氦气透平压气机设计。在主氦风机研制方面,顺利完成了10 MW高温气冷堆(HTR-10)主氦风机研制与高温气冷堆示范电站(HTR-PM)主氦风机研制,获得了主氦风机完整的性能数据。为进一步确保HTR-PM项目的顺利推进,搭建了主氦风机综合试验平台,同时测试了2种主氦风机(电磁轴承主氦风机和干气密封主氦风机)的性能。取得的研究成果体现了清华大学核能与新能源技术研究院在自主研发先进核能核心装备技术上取得了重大突破。Modular high temperature gas-cooled reactors(HTGRs)have inherent safety characteristics with high reactor outlet temperatures which can be coupled with closed Brayton or Rankine cycles to provide efficient power generation.The helium turbo-compressors and circulators are essential power components that couple the HTGRs with these two cycles.This research investigated the steady-state and dynamic thermodynamic characteristics for a closed helium Brayton cycle for two helium turbo-compressor designs,the 2.2 MW prototype and a 120 MW commercial helium turbo-compressor.Helium circulators were also developed for the 10 MW HTGR(HTR-10)and the HTGR demonstration plant(HTR-PM)with complete performance data for the helium circulators.An experimental platform was then built to test the two types of helium circulators,one with magnetic bearings and one with dry gas seals.This research shows that the Institute of Nuclear and New Energy Technology,Tsinghua University,has developed helium turbo-compressors and circulators for advanced nuclear power plants.

关 键 词：高温气冷堆(HTGR) 氦气透平压气机 主氦风机 闭式Brayton循环 

分 类 号：TL424[核科学技术—核技术及应用]