4.7 Article

High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments

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JOURNAL OF NUCLEAR MATERIALS
卷 440, 期 1-3, 页码 420-427

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ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2013.05.047

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  1. U.S. Department of Energy's Office of Nuclear Energy, Advanced Fuel Campaign of the Fuel Cycle RD program

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Alternative fuel cladding materials to Zr alloys are being investigated for enhanced accident tolerance, which specifically involves oxidation resistance to steam or steam-H-2 environments at >= 1200 degrees C for short times. Based on a comparison of a range of commercial and model alloys, conventional austenitic steels do not have sufficient oxidation resistance with only similar to 18Cr-10Ni. Higher alloyed type 310 stainless steel is protective but Ni is not a desirable alloy addition for this application. Results at 1350 degrees C indicated that FeCrAl alloys and CVD SiC remain oxidation resistant in steam. At 1200 degrees C, high (>= 25% Cr) ferritic alloys appear to be good candidates for this application. Higher pressures (up to 20.7 bar) and H-2 additions appeared to have a limited effect on the oxidation behavior of the most oxidation resistant alloys, but higher pressures accelerated the maximum metal loss for less oxidation resistant steels and less metal loss was observed for type 317 L tubing in a H-2-50%H2O environment at 10.3 bar compared to 100% H2O. (C) 2013 Elsevier B.V. All rights reserved.

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