Irradiation-induced impurity segregation and ductile-to-brittle transition temperature shift in high chromium ferritic/martensitic steels

A model is presented to predict irradiation-induced impurity segregation and its contribution to the ductile-to-brittle transition temperature (DBTT) shift in high chromium ferritic steels. The hardening contribution (dislocation loops, voids and precipitates) is also considered in this study. The p...

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Published inJournal of nuclear materials Vol. 367; pp. 621 - 626
Main Authors Lu, Z., Faulkner, R.G., Flewitt, P.E.J.
Format Journal Article Conference Proceeding
LanguageEnglish
Published Amsterdam Elsevier B.V 01.08.2007
Elsevier
Subjects
Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Nuclear fuels
Grain size
Ductile brittle transition
Hardening
Martensitic steel
Impurity
Chromium
Ferritic steel
High temperature
Nuclear reactor
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Summary:A model is presented to predict irradiation-induced impurity segregation and its contribution to the ductile-to-brittle transition temperature (DBTT) shift in high chromium ferritic steels. The hardening contribution (dislocation loops, voids and precipitates) is also considered in this study. The predicted results are compared with the experimental DBTT shifts data for irradiated 9Cr1MoVNb and 12Cr1MoVW steels with different grain sizes.
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ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2007.03.039