Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Technology Pub Date : 2024-07-02 DOI:10.1080/00295450.2024.2361187

J. Liao, C. A. Stansbury, M. E. Durse, D. L. Wise, E. Tatli, T. G. Loebig, R. F. Wright, P. Ferroni, S. J. Lee, M. Epstein, M. Caramello, M. Frignani, M. Tarantino, G. Grasso, I. Di Piazza, S. Bassini, P. Lorusso, A. Antonelli, D. Martelli, A. Wimshurst, R. Watkins, G. Macpherson, D. Wilson, H. Iacovides, A. Cioncolini, J. Francis, J. Buckley

引用次数: 0

Abstract

The Westinghouse lead-cooled fast reactor (LFR) is a next-generation nuclear power plant whose primary mission is to reduce front-end capital costs and generate flexible and cost-competitive electr...

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支持英国先进模块化反应堆计划的领先快堆热液压测试设施

西屋公司的铅冷快堆是下一代核电站，其主要任务是降低前端资本成本，产生灵活且具有成本竞争力的电力。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear Technology 工程技术-核科学技术

CiteScore

3.40

自引率

6.70%

发文量

116

审稿时长

4-8 weeks

期刊介绍： Nuclear Technology aims to be the leading international publication reporting new information in the practical applications of nuclear science and technology. We publish technical papers, technical notes, critical reviews, rapid communications, book reviews, and letters to the editor on all phases of applications of fundamental research to nuclear technology.