(High-temperature reactor materials for gas-cooled reactor)

Technical Report · Mon Sep 17 04:00:00 EDT 1990

OSTI ID:6623404

Haggag, F M

The traveler participated in an information exchange under the US/FRG/Swiss Umbrella Agreement on high-temperature reactor materials for gas-cooled reactor development at Forschungszentrum Juelich GmbH (KFA), FRG, August 30--31, 1990. The traveler presented the US results of the first four irradiation capsules and discussed some of the radiation-induced damage mechanisms and compared our data to previously obtained German data (good comparison was noted). Dr. F. Schubert of KFA expressed interest in incorporating a set of miniature tensile specimens (to be machined by KFA from German pressure vessel steel intended for use in their HTGRs) in one of our future ORNL irradiation capsules. It was agreed that this is feasible. Incorporating the German material in our program will increase our data base and knowledge of effects of irradiation on materials and particularly the influence and contribution of chemical composition and fabrication conditions on radiation embrittlement. The traveler also visited the KFA high-temperature reactor materials laboratory and was briefed on their activities. Prior to visiting KFA, the traveler presented a paper on small specimen techniques to measure radiation damage in pressure vessel steels at the Seventh ASTM-EURATOM Symposium on Reactor Dosimetry, Strasbourg, France, August 27--28, 1990. The paper was displayed in a poster session for two days, which gave the traveler the opportunity for several individual discussions and to exchange ideas with researchers from various countries.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6623404
• Report Number(s): ORNL/FTR-3725; ON: DE90017730
• Country of Publication: United States
• Language: English

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