Topic
Zirconium alloy
About: Zirconium alloy is a research topic. Over the lifetime, 6548 publications have been published within this topic receiving 78954 citations. The topic is also known as: zircaloy.
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TL;DR: In this article, the initiation mechanism of nanoscale pores in the oxide films formed on zirconium alloys was investigated, and it was shown that these porosity is generated by the enrichment of Y at columnar oxide grain boundaries and subsequent unequal diffusion of Zr and Zr cations in oxide crystals.
38 citations
TL;DR: In this paper, the corrosion characteristics of Zircaloy-4 have been investigated in various aqueous solutions of LiOH, NaOH, KOH, RbOH and CsOH with equimolar M + and OH − at 350°C.
38 citations
TL;DR: In this paper, the corrosion behavior of Zr-1.5Nb-0.4Sn−0.1Cr (HANA-4), Zr−1.1Nb −0.3Sn− 0.05Cu (Hana-6), and Zr −1.2Fe−0,0.2Cr (Zry4) in weight percent was investigated in a 360°C water loop containing 2.2
38 citations
38 citations
Patent•
14 Mar 1984TL;DR: In this paper, the zirconium base alloys have been designed to minimize the adverse effects of pellet-clad interaction, when they are used as a liner bonded to the inside surface of water reactor nuclear fuel cladding.
Abstract: The present invention pertains to zirconium base alloys containing about 0.1 to 0.6 weight percent tin; about 0.07 to 0.24 weight percent iron; about 0.05 to 0.15 weight percent chromium; and up to about 0.05 weight percent nickel. The balance of the alloy is zirconium with incidental impurities. The levels of the incidental impurity, oxygen, is controlled to a level of less than about 350 ppm. These alloys have been designed to minimize the adverse effects of pellet-clad interaction, when they are used as a liner bonded to the inside surface of water reactor nuclear fuel cladding. Specific cladding and fuel element designs according to the present invention are described.
38 citations