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Status of Structural Design Code for Metallic High-Temperature Gas-Cooled Reactor Components

Hubertus Nickel, Florian Schubert

Nuclear Technology / Volume 66 / Number 3 / September 1984 / Pages 649-660

H. Design Codes and Life Prediction / Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material / dx.doi.org/10.13182/NT84-A33486

Based on the existing structural design code for pressure vessel and nuclear light water reactor power stations, situations for metallic structures in hightemperature gas-cooled reactors (HTGRs) are described for those metallic structures that mainly operate in temperature ranges of time-independent and time-dependent materials properties. The ASME Code Case N 47 is critically reviewed. For advanced HTGRs with components for operating temperatures >800°C, no nuclear accepted structural design code exists. The status of the ongoing work for the basis of those codes is given with the main emphasis on the situation in the Federal Republic of Germany.