Study on Research and Development System of Materials for Sodium-Cooled Fast Reactor Technology

WANG Qi-an,LONG Bin,WANG Xi-tao,FANG Yu-cheng,ZHANG Dong-hui,ZHOU Pei-de

Journal of Iron and Steel Research ›› 2014, Vol. 26 ›› Issue (9) : 1-6.

Journal of Iron and Steel Research ›› 2014, Vol. 26 ›› Issue (9) : 1-6. DOI: 10.13228/j.boyuan.issn1001-0963.20130275

Study on Research and Development System of Materials for Sodium-Cooled Fast Reactor Technology

  • WANG Qi-an1,LONG Bin2,WANG Xi-tao3,FANG Yu-cheng4,ZHANG Dong-hui2,ZHOU Pei-de2
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Abstract

Sodium-cooled fast reactor (SFR) is the main type of reactor in Gen-IV nuclear energy system, and it is the important choice on nuclear power technology to realize the closed fuel recycle system and sustainable development in China. Most of the key structural unit were imported from abroad, which restricts the development of the SFR in China. According to the strategy of engineering and commercialization of SFR in China, a review is given on the current research and development situation of materials for SFR in China and some related key issues are given. At the same time, a roadmap for SFR material development is also proposed and some related key tasks are introduced. The aim of the study is to provide reference for the development of sodium-cooled fast reactor technology in China.

Key words

Sodium-cooled fast reactor / R&D on materials / Technology road map

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WANG Qi-an,LONG Bin,WANG Xi-tao,FANG Yu-cheng,ZHANG Dong-hui,ZHOU Pei-de. Study on Research and Development System of Materials for Sodium-Cooled Fast Reactor Technology[J]. Journal of Iron and Steel Research, 2014, 26(9): 1-6 https://doi.org/10.13228/j.boyuan.issn1001-0963.20130275

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