Citation

Nickel H, Bodmann E, Seehafer HJ. Energy 1991; 16(1-2): 221-242.

Copyright

(Copyright © 1991, Elsevier Publishing)

DOI

10.1016/0360-5442(91)90102-R

PMID

unavailable

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.

The special features of the HTGR which provide a high degree of safety are the use of ceramics for the core construction and the low power density of the core. The reactor integrity concept which has been developed is based on these two characteristics.

Previously, technical guidelines and design codes for nuclear plants were tailored exclusively to light water reactor systems. An extensive research project was therefore initiated which led to the formulation of the basic principles on which a high temperature design code can be based.