SYMPOSIA PAPER Published: 01 January 1999
STP13895S

Tensile Properties of a Titanium Modified Austenitic Stainless Steel and the Held Joints after Neutron Irradiation

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Tensile specimens of a titanium modified austenitic stainless steel and its weldments fabricated with Tungsten Inert Gas (TIG) and Electron Beam (EB) welding techniques were irradiated to a peak dose of 19 dpa and a peak helium level of 250 appm in the temperature range between 200 and 400° C in spectrally tailored capsules in the Oak Ridge Research Reactor (ORR) and the High Flux Isotope Reactor (HFIR). The He/dpa ratio of about 13 appm/dpa is similar to the typical helium/dpa ratio of a fusion reactor environment. The tensile tests were carried out at the irradiation temperature in vacuum. The irradiation caused an increase in yield stress to levels between 670 and 800 MPa depending on the irradiation temperature. Total elongation was reduced to less than 10%, however the specimens failed in a ductile manner. The results were compared with those of the specimens irradiated using irradiation capsules producing larger amount of He. Although the He/dpa ratio affected the microstructural change, the impact on the post irradiation tensile behavior was rather small not only for base metal specimens but also for the weld joint and the weld metal specimens.

Author Information

Shiba, K
Japan Atomic Energy Research Institute, Tokai-mura Ibaraki-ken, Japan
Ioka, I
Japan Atomic Energy Research Institute, Tokai-mura Ibaraki-ken, Japan
Jitsukawa, S
Japan Atomic Energy Research Institute, Tokai-mura Ibaraki-ken, Japan
Hamada, S
Japan Atomic Energy Research Institute, Tokai-mura Ibaraki-ken, Japan
Hishinuma, A
Japan Atomic Energy Research Institute, Tokai-mura Ibaraki-ken, Japan
Robertson, JP
Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN, USA
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Details
Developed by Committee: E10
Pages: 659– 670
DOI: 10.1520/STP13895S
ISBN-EB: 978-0-8031-5395-0
ISBN-13: 978-0-8031-2614-5