In-reactor creep behavior of selected ferritic alloys [electronic resource].
- Pittsburgh, Pa. : Westinghouse Electric Corporation, 1983.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 24 : digital, PDF file
- Additional Creators:
- Westinghouse Electric Corporation
United States. Department of Energy. Office of Scientific and Technical Information
- An experiment was conducted in the Experimental Breeder Reactor-II (EBR-II) to investigate the in-reactor creep behavior of selected ferritic alloys. Pressurized tube creep specimens fabricated from the following ferritic alloys: HT-9, 9Cr-2Mo, and 2-1/4Cr-1Mo, were irradiated in EBR-II to a peak fluence of 2.8 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV) and at irradiation temperatures of 443, 505 and 572/sup 0/C. Each alloy had four specimens with midwall hoop stresses of 0, 50, 75 and 100 MPa at each irradiation temperature. Measurements of the zero-stressed specimens indicate that none of the ferritic alloys are exhibiting evidence for swelling or phase transformations at these irradiation temperatures and at a fluence of 2.8 x 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV).
- Published through SciTech Connect.
TMS/AIME topical conference on ferritic alloys for use in nuclear energy technologies, Snowbird, UT, USA, 19 Jun 1983.
Puigh, R.J.; Wire, G.L.
- Funding Information:
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