Author:
Than Y.R.,Grimes R.W.,Bell B.D.C.,Wenman M.R.
Funder
Singapore Nuclear Research and Safety Institute
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference53 articles.
1. Zirconium Alloys in Nuclear Technology;Krishnan,1981
2. The development of the zircaloys. In Corrosion of zirconium alloys;Kass,1964
3. Corrosion behavior of Zircaloy-4 cladding with varying tin content in high-temperature pressurized water reactors;Garde,1994
4. Improvement of the uniform corrosion resistance of Zircaloy-4 in the absence of irradiation;Charquet;J. Nucl. Mater.,1988
5. Circumferential creep properties of stress-relieved Zircaloy-4 and Zr-Nb-Sn-Fe cladding tubes;Lee;J. Nucl. Mater.,2009
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