Engineering test of HTR-PM helical tube once through steam generator

被引：0
|
作者：
Li X. [1 ]
Wu X. [1 ]
Zhang Z. [1 ]
Zhao J. [1 ]
Luo X. [1 ]
机构：
[1] Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Collaborative Innovation Center for Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing
来源：
Qinghua Daxue Xuebao/Journal of Tsinghua University | 2021年 / 61卷 / 04期
关键词：
Engineering test; High temperature gas-cooled reactor (HTGR); Steam generator; Temperature uniformity; Two phase flow instability;
D O I：
10.16511/j.cnki.qhdxxb.2021.25.029
中图分类号：
学科分类号：
摘要：
Scale engineering tests are necessary when developing a steam generator. An engineering test facility for the steam generator (ETF-SG) was built for HTR-PM at the Institute of Nuclear and New Energy Technology (INET), Tsinghua University. ETF-SG can simulate the HTR-PM steam generator operating parameters for full scale tests of one helical tube assembly. The design thermal power is 10 MW. The design temperature and pressure of the primary helium loop are 800℃ and 8 MPa. The design temperature and pressure of the secondary loop are 600℃ and 18 MPa. Thus, ETF-SG can be used for full scale engineering tests of the test steam generator. More than twenty thermal hydraulic experiments have been finished. The tests experimentally investigated the temperature uniformity, transient thermal hydraulic response, temperature uniformity after tube plugging and adjustments, two phase flow instability and other conditions. The tests verified the thermal hydraulic and structural designs of the HTR-PM steam generator. These experiments provide important data for the commissioning and operation of the HTR-PM nuclear power plant. © 2021, Tsinghua University Press. All right reserved.
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页码：329 / 337
页数：8
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