期刊首页 优先出版 当期阅读 过刊浏览 作者中心 关于期刊 English

《工程(英文)》 >> 2016年 第2卷 第1期 doi: 10.1016/J.ENG.2016.01.022

铅冷快堆:未来的机会?

Ansaldo Nucleare SpA, Genova 16159, Italy

修回日期: 发布日期: 2016-03-31

下一篇 上一篇

参考文献

[ 1 ] US DOE Nuclear Energy Research Advisory Committee, Generation IV International Forum. A technology roadmap for Generation IV nuclear energy systems. USA: US DOE Nuclear Energy Research Advisory Committee, Generation IV International Forum; 2002. Report No.: GIF-002-00.

[ 2 ] GIF Policy Group. Technology roadmap update for Generation IV nuclear energy systems. USA: The OECD Nuclear Energy Agency for the Generation IV International Forum; 2014Jan.

[ 3 ] Alemberti A, Frogheri ML, Hermsmeyer S, Smirno LAV, Takahashi M, Smith CF, Lead-cooled fast reactor (LFR) risk and safety assessment white paper, revision 8 [Internet]. [cited 2014Apr]. Available from: https://www.gen-4.org/gif/upload/docs/application/pdf/2014-11/rswg_lfr_white_paper_final_8.0.pdf.

[ 4 ] Weeks JR. Lead, bismuth, tin a nd their alloys as nuclear coolants. Nucl Eng Des 1971; 15: 363−72. 链接1

[ 5 ] Smirnov VS. Lead-cooled fast reactor BREST−project status and prospects [presentation]. In: International Workshop on Innovative Nuclear Reactors Cooled by Heavy Liquid Metals: Status and Perspectives; 2012Apr17−20; Pisa, Italy; 2012.

[ 6 ] Alemberti A, Frogheri M, Mansani L. The lead fast reactor: demonstrator (ALFRED) and ELFR design [presentation]. In: International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13); 2013Mar4−7; Paris, France; 2013.

[ 7 ] Takahashi M. National status on LFR development in Japan [presentation]. In: 11th LFR Prov. SSC Meeting; 2012Apr16; Pisa, Italy; 2012.

[ 8 ] Choi S, Hwang IS, Cho JH, Shim CB. URANUS: Korean lead-bismuth cooled small modular fast reactor activities. In: Proceedings of ASME 2011 Small Modular Reactors Symposium; 2011Sep28−30; Washington, DC, USA. ASME Digital Collection; 2011. p. 107−12.

[ 9 ] Smith CF, Halsey WG, Brown NW, Sienicki JJ, Moisseytsev A, Wade DC. SSTAR: the US lead-cooled fast reactor (LFR). J Nucl Mater 2008; 376(3): 255−9. 链接1

[10] Wu YC, Bai YQ, Song Y, Huang QY, Zhao ZM, Hu LQ. Development strategy and conceptual design of China lead-based research reactor. Ann Nucl Energy 2016; 87(Part 2): 511−6. 链接1

相关研究