Pod corrosion
Introduction
Zirconium alloys are solid solutions of zirconium with other metals, a subgroup of them are the trademark Zircaloy. Zirconium has a very low thermal neutron absorption cross section, high hardness, ductility and corrosion resistance. One of the main applications of zirconium alloys is nuclear technology, as fuel cladding material in nuclear reactors, especially water reactors. A typical nuclear-grade zirconium alloy composition includes more than 95% zirconium by weight[1] and less than 2% tin, niobium, iron, chromium, nickel and other metals, added to improve mechanical properties and corrosion resistance.[2].
Water cooling of zirconium alloys requires better resistance to oxidation associated with galvanic corrosion. Furthermore, the oxidation reaction of zirconium with water releases hydrogen in the form of gas, which partly diffuses into the metal and forms zirconium hydrides. Hydrides are less dense and mechanically more fragile than the alloy, their formation causes blisters and ruptures in the sheaths. A phenomenon known as hydrogen embrittlement.[3].
References
- [1] ↑ La composición de las aleaciones se expresa generalmente en masa.
- [2] ↑ Mary Eagleson (1994).Concise encyclopedia chemistry . Walter de Gruyter. pp. 1199–. ISBN 978-3-11-011451-5. Publicado el 18 de marzo de 2011.: http://books.google.ch/books?id=Owuv-c9L_IMC&pg=PA1199&redir_esc=y#v=onepage&q&f=false
- [3] ↑ Delayed hydride cracking in zirconium alloys in pressure tube nuclear reactors, Final report of a coordinated research project 1998–2002, IAEA, October 2004.: http://www-pub.iaea.org/MTCD/publications/PDF/te_1410_web.pdf