Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses

Research output: Contribution to journalArticle

Authors

Institutes & Expert groups

Documents & links

Abstract

Understanding the behavior of reactor pressure vessel (RPV) steels under irradiation is a mandatory task that has to be elucidated in order to be able to operate safely a nuclear power plant or to extend its lifetime. To build up predictive tools, a substantial experimental data base is needed at the nanometre scale to extract quantitative information on neutron-irradiated materials and to validate the theoretical models. To reach this experimental goal, ferritic model alloys and French RPV steel were neutron irradiated in a test reactor at an irradiation flux of 9 x 10(17) nm(-2) s, doses from 0.18 to 1.3 x 10(24) nm(-2) and 300 degrees C. The main goal of this paper is to report the characterization of the radiation-induced microstructural change in the materials by using the state-of-the-art of characterization techniques available in Europe at the nanometre scale. Possibilities, limitations and complementarities of the techniques to each other are highlighted.

Details

Original languageEnglish
Pages (from-to)73-83
JournalJournal of Nuclear Materials
Volume406
Issue number1
DOIs
Publication statusPublished - 1 Nov 2010

Keywords

  • RPV steels, Microstructure, Neutron irradiation, Radiation damage, APT, TEM, PAS, SANS

ID: 297642