REVIEW ARTICLE

Effects of irradiation on chromium’s behavior in ferritic/martensitic FeCr alloy

  • Xinfu HE ,
  • Wen YANG ,
  • Zhehao QU ,
  • Sheng FAN
Expand
  • China Institute of Atomic Energy, Beijing 102413, China

Received date: 10 Nov 2008

Accepted date: 05 Jan 2009

Published date: 05 Jun 2009

Copyright

2014 Higher Education Press and Springer-Verlag Berlin Heidelberg

Abstract

The effects of irradiation on chromium performance under different temperatures in Fe-20at%Cr were modeled by modified Marlowe code. Chromium precipitation was observed in FeCr alloy after irradiation; interstitial Chromium atoms are the preferred formation of mixed Fe-Cr dumbbells in the direction of<110>and<111>; interstitial chromium atoms congregated on {111} and {110} plane. The results are compared with experiment observations and are useful to understanding the irradiation performances of FeCr alloy.

Cite this article

Xinfu HE , Wen YANG , Zhehao QU , Sheng FAN . Effects of irradiation on chromium’s behavior in ferritic/martensitic FeCr alloy[J]. Frontiers in Energy, 0 , 3(2) : 181 -183 . DOI: 10.1007/s11708-009-0025-x

Acknowledgements

This work was funded by the National Basic Research Program of China (No. 2007CD209801). The author would like to thank Mark T. Robinson for providing the Marlowe code, and Prof. Yu Jinnan and Wu Xuezhi for their intelligent discussion.
1
Wallenius J. Modeling of chromium precipitation in Fe-Cr alloy. Phys Rev B, 2004, 69(9): 094103-094111

DOI

2
Malerba L, Terentyev D A, Bonny G, . Modeling of radiation damage in Fe-Cr alloy. Journal of ASTM International. 2007, 4(6): 1-19

DOI

3
Miller M, Hyde J, Cerezo A, . Comparison of low temperature decomposition in Fe-Cr and duplex stainless steels. Applied Surface Science, 1995, 87-88: 323-328

DOI

4
Mathon M H, de Carlan Y, Geoffroy G, . A SANS investigation of the irradiation-enhanced α-α′ phases separation in 7-12 Cr martensitic steels. J Nucl Mat, 2003, 312(2,3): 236-248

5
Pearson W B. A Handbook of Lattice Spacings and Structures of Metals and Alloys. Belfast: Pergamon Press, 1958, 532

6
Yoshitake T, Yamagata I, Allen T R, . Behavior of irradiated type 316 stainless steels under low-strain-rate tensile conditions. Journal of ASTM International, 2005, 2(3): 162-173

DOI

7
Konishi T, Ohsawa K, Abe H, . Determination of N-body potential for Fe-Cr alloy system and its application to defect study. Computational Materials Science, 1999, 14(1-4): 108-113

DOI

8
Wallenius J, Abrikosov I A, Chakarova R, . Development of an EAM potential for simulation of radiation damage in Fe–Cr alloys. Journal of Nuclear Materials, 2004, 329-333(11): 1175-1179

DOI

9
Malerba L, Terentyev D A, Olsson P, . Molecular dynamics simulation of displacement cascades in Fe–Cr alloys. Journal of Nuclear Materials. 2004, 329-333(11): 1156-1160

DOI

10
Mendelev M I, Han S, Srolovitz D J, . Development of new interatomic potentials appropriate for crystalline and liquid iron. Philosophical Magazine, 2003, 83(35): 3977-3994

DOI

11
Đogo H. Properties of point defects in Fe–Cr alloys. 2006, http://energy-environment.vin.bg.ac.yu/presentations/SixBestPosters/H.DJOGO/Vrnjacka%20Banja.ppt

12
Chen Jiachao, Yu Gang. Characterization of dislocation loop in bcc ferritic steel by TEM observation and MD simulation. 9th International Conference on Computer Simulation of Radiation Effects in Solids, Beijing, 2008, 42

13
Gupta G, Was G S. Effect of proton irradiation and grain boundary engineering on stress corrosion cracking of Ferritic-Martensitic alloys in supercritical water. Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System–Water Reactors. Salt Lake City, Utah, 2005

14
Eyre B L, Bullough R. On the formation of interstitial loops in b.c.c. metals. Philos Mag, 1965, 12(1): 31-39

DOI

Outlines

/