发明名称 HEAT TREATMENT OF ZIRCONIUM ALLOY
摘要 PURPOSE:To markedly enhance the corrosion resistance of Zr alloy, in a method for processing the Zr alloy for a nuclear reactor, by subjecting the Zr alloy to solid solution treatment under a specific condition prior to cold working after hot rolling is completed. CONSTITUTION:An ingot, which is prepared by a method wherein Zr sponge and an alloying element are molded and the molded object is cast after vacuum melting, is subjected to hot forging and succeedingly subjected to solid solution treatment to carry out hot rolling. The rolled alloy is subsequently heated to 860-1,000 deg.C in the region of the (alpha+beta) structure without carrying out cold rolling to carry out solid solution treatment. This treated alloy is subjected to cold rolling, annealing, pickling and polishing to obtain a product. By this solid solution treatment after hot rolling as referred above, elements such as Fe, Cr or Ni and impurities are diffused effectively and corrosion resistance can be markedly enhanced.
申请公布号 JPS5822368(A) 申请公布日期 1983.02.09
申请号 JP19810121446 申请日期 1981.08.04
申请人 NIPPON KOGYO KK 发明人 KONISHI ATSUO;YAMADA RIYUUZOU;YAGI YOSHIO;KATOU YOSHINORI
分类号 C22F1/18 主分类号 C22F1/18
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