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Fatigue tests in vacuum and air were carried out on solution-annealed 316L stainless steel specimens (NET reference material) in push-pull type, load-controlled experiments at 20, 150 and 425 C. Reference specimens were compared to specimens which had been exposed to the plasma of the TEXTOR tokamak prior to testing. It was found that the surface modifications caused by the TEXTOR exposure led to fatigue life deterioration by factors between 2 (at 20 C) and 6 (at 425 C). Possible reasons for this degradation are discussed.

Additional information

Authors: ULLMAIER H ET AL., Institut für Festkörperforschung, Kernforschungsanlage Jülich GmbH, Jülich (DE);FAULKNER R G, University of Loughborough, IPTME, Loughborough (GB);LITTLE E A, Harwell Laboratory, Materials Development Division, Didcot, Oxon. (GB);WIENHOLD P, Institut für Plasmaphysik, Kernforschungsanlage Jülich GmbH, Jülich (DE)
Bibliographic Reference: Article: Journal of Nuclear Materials, Vol. 175 (1990) pp. 20-28
Record Number: 199110560 / Last updated on: 1994-12-02
Original language: en
Available languages: en