volume 238, issue 2, P310-321 2008
DOI: 10.1016/j.nucengdes.2006.09.010
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Abstract: Low-carbon, nitrogen-controlled 316 stainless steel is regarded as a principal candidate for a main structural material of future fast breeder reactor plants in Japan. To grasp creep deformation and rupture behavior of this steel whose modeling is indispensable in the design of high-temperature components, a number of uniaxial tensile creep tests have been conducted for four products of this steel at 550 • C and higher temperatures. Long-term creep rupture data up to about 94,000 h were obtained and used to e…

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