Published: Jan 1990
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Irradiation creep was investigated in the alloys—prime candidate alloy (PCA), Japanese Fusion Energy Program (JPCA), and American Iron and Steel Institute (AISI) 316 (UNS S31600) stainless steel. Tubes pressurized to stress levels of 50 to 400 MPa were irradiated in the Oak Ridge Research Reactor (ORR) with the neutron spectrum tailored to achieve the fusion reactor helium:dpa value of 12 appm/dpa in AISI 316 stainless steel. Irradiation temperatures of 60, 330, and 400°C were investigated, and the irradiation produced 8 dpa and a maximum of about 100 appm helium. Irradiation creep rates of 2.2 to
irradiation creep, fusion, stainless steel, creep
Grossbeck, Martin L.
Research staff member, Oak Ridge National Laboratory, Oak Ridge, TN
Mansur, L. K.
Group leader, Oak Ridge National Laboratory, Oak Ridge, TN
Tanaka, M. P.
Principal research engineer, Japan Atomic Energy Research Institute, Tokyo,