Abstract
Important Generation IV criteria for advanced fuel cycles are both improved efficiency and economical competitiveness. To reach these goals and keep high safety standards a key item is the availability of suitable structural materials. Ferritic/Martensitic (F/M) and Oxide-Dispersion-Strengthened (ODS) steels are indicated as the most promising candidates to withstand temperature, stress and irradiation fields expected in the core and primary system of most of the new generation reactors. In this context, the "Generation IV and Transmutation Materials" (GETMAT) project, sponsored by the EC, will contribute to the characterisation of ODS and F/M steels. The experimental and phenomenological aspects are complemented by the development of physical models aimed at describing and possibly predicting materials performance in operation.
Original language | English |
---|---|
Pages (from-to) | 3514-3520 |
Number of pages | 7 |
Journal | Nuclear Engineering and Design |
Volume | 241 |
Issue number | 9 |
DOIs | |
State | Published - Sep 2011 |
Funding
The authors acknowledge the scientific and technical staff at the universities, research associations and utility involved in the GETMAT project. This work is supported by the European Commission under the FP7 Grant Agreement FP7-212175 .
Funders | Funder number |
---|---|
EC - European Commission | FP7-212175 |
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- General Materials Science
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering