Westinghouse Test Facilities for Lead Fast Reactor Development

被引:2
|
作者
Lee, Sung Jin [1 ]
Ickes, Michael [2 ]
Arndt, Jeffrey L. [2 ]
Epstein, Michael [1 ]
Patel, Asfaq [3 ]
Ferroni, Paolo [2 ]
机构
[1] Fauske & Associates, Burr Ridge, IL 60527 USA
[2] Westinghouse Elect Co LLC, Cranberry, PA USA
[3] Westinghouse Elect Co UK Ltd, Preston, England
关键词
Lead-cooled fast reactor; lead coolant; lead freezing; liquid-lead corrosion;
D O I
10.1080/00295450.2023.2197667
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Westinghouse is developing a lead-cooled fast reactor (LFR) as its next-generation utility-scale nuclear power plant. To support its development, Westinghouse and its partners are building 10 test facilities to demonstrate key LFR phenomena, materials, and components in liquid lead. These test infrastructures are distributed across several institutions, and this paper focuses on those located within Westinghouse. It describes three state-of-the-art test rigs being installed in the Westinghouse facility in Springfields, United Kingdom, to test materials in liquid lead and to investigate key LFR phenomena, which will also be used to validate modeling and simulation tools. These facilities address material corrosion/erosion testing (MELECOR), lead freezing and under-lead viewing testing (LEFREEZ), and primary heat exchanger failure testing (LEWIN). This paper also describes the first liquid-lead test system to become operational at Westinghouse at the company's site in Churchill, Pennsylvania, i.e., a test rig named HELMET to conduct tensile tests in a molten-lead environment to investigate the potential susceptibility of LFR candidate materials to liquid-metal embrittlement.
引用
收藏
页码:666 / 680
页数:15
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