Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels

R. B. Rebak, E. Dolley, Wanming Zhang, R. Umretiya, A. Hoffman
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Abstract

Iron-chromium-aluminum (FeCrAl) alloys are being characterized to be used in light water reactors for the cladding of the fuel. This family of alloys were never used before in a reactor environment so their behavior should be evaluated. This manuscript describes the enhanced mechanical properties and thermal creep resistance of two FeCrAl alloys (PMC26M & FA-SMT or APMT-2) as compared with the current Zircaloy-2 based cladding. At 450°C and under a nominal hoop stress of 138 MPa (20ksi), Zircaloy-2 tubes suffer rapid creep while the two FeCrAl alloys do not show any evidence of creep at a higher nominal hoop stress of 324 MPa (47 ksi). FA-SMT had higher creep resistance than PMC26M at 600°C and 800°C mainly due to precipitate strengthening in FA-SMT.
轻水反应堆燃料铁铬铝包层力学性能的增强
铁铬铝(FeCrAl)合金的特点是用于轻水反应堆的燃料包层。这类合金以前从未在反应堆环境中使用过,因此应该对它们的行为进行评估。本文描述了两种FeCrAl合金(PMC26M & FA-SMT或APMT-2)与目前的锆合金-2基包层相比,增强的机械性能和耐热蠕变性能。在450°C和138mpa (20ksi)的名义环向应力下,锆合金-2管遭受快速蠕变,而两种FeCrAl合金在更高的324mpa (47ksi)的名义环向应力下没有任何蠕变迹象。在600°C和800°C时,FA-SMT的抗蠕变性能高于PMC26M,这主要是由于FA-SMT中析出相的强化。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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