The materials program for the HTR in the frg: Integrity concept, status of the development of high temperature materials and design codes

H. Nickel, E. Bodmann and H.J. Seehafer

Energy, 1991, vol. 16, issue 1, 221-242

Abstract: During the last 15 years, the research and development of materials for high temperature gas-cooled reactor (HTGR) applications in the Federal Republic of Germany have been concentrated on the qualification of hightemperature structural alloys. Such materials are required for heat exchanger components of advanced HTGRs supplying nuclear process heat in the temperature range between 750 ° and 950 °C. The suitability of the candidate alloys for service in the HTGR has been established and continuing research is aimed at verification of the integrity of components over the envisaged service lifetimes.

Date: 1991
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Persistent link: https://EconPapers.repec.org/RePEc:eee:energy:v:16:y:1991:i:1:p:221-242

DOI: 10.1016/0360-5442(91)90102-R

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