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Multi-scale modeling of radiation damage in FeCr alloy

He Xin-Fu Yang Wen Fan Sheng

Multi-scale modeling of radiation damage in FeCr alloy

He Xin-Fu, Yang Wen, Fan Sheng
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  • Abstract views:  3855
  • PDF Downloads:  1651
  • Cited By: 0
Publishing process
  • Received Date:  07 January 2009
  • Accepted Date:  18 March 2009
  • Published Online:  20 December 2009

Multi-scale modeling of radiation damage in FeCr alloy

  • 1. 中国原子能科学研究院,北京 102413

Abstract: Since irradiation experiments of ferritic/martensitic (F/M) FeCr alloys show that F/M steels undergo much less swelling than austenitic steels during neutron or charged particle irradiation,in addition, it is well-known that high chromium content of F/M alloys provide good resistance against corrosion, they are considered as one of the most attractive candidate materials for future nuclear facilities, such as Fusion Reactor, ADS and generation Ⅳ reactors. Although irradiation experiments can not be replaced by modeling, a purely experimental approach to understanding the effects of irradiation is also not practicable, so in recent years substantial progress has been made in the field of multi-scale modeling of radiation damage in F/M FeCr alloys. The present paper is a review of methods used and results achieved within the last couple of years, and some suggestions are put forward for the further improvements.

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