Development and qualification of materials for structural components for the high-temperature gas-cooled reactor-Reference-Cited by-同舟云学术

Development and qualification of materials for structural components for the high-temperature gas-cooled reactor

Published:1990-07 Issue:2 Volume:121 Page:183-192
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Nickel H.,Schubert F.,Breitling H.,Bodmann E.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference16 articles.

1. Proceedings of the Workshop on “Structural Design Criteria for HTR”, Jüll-Conf-71,1989

2. Influence of radiation damage mechanisms on the load signal and on the transition curve of instrument impact testing;Pachur;J. Nucl. Mater.,1988

3. Metallische Werkstoffe für HTR,1982

4. Special issues on high-temperature gas-cooled reactor materials,1984

5. Alloy 800: New stress rupture and creep data for pressurized components in high temperature reactors;Diehl,1988

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