Journal Menu► ▼ Journal Menu
Journal Browser► ▼ Journal Browser
Special Issue "Zirconium Alloys"
A special issue of Metals (ISSN 2075-4701).
Deadline for manuscript submissions: closed (30 April 2018).
Zirconium alloys are used as the primary structural components in the nuclear power industry, because of their low thermal neutron absorption cross section, high corrosion resistance, good ductility, and satisfactory strength. In general, several interconnected problems are given special attention: (1) Corrosion. Corrosion of zirconium alloys is one of the main factors in the degradation of zirconium alloys during service. The surface reaction between the zirconium cladding and the coolant water in nuclear reactors leads to the oxidation of the cladding and the release of hydrogen. The pick-up of hydrogen in zirconium alloys induces the embrittlement of the tubes due to hydride formation. Therefore, there is great incentive to minimize the amount of oxidation and hydriding that materials experience in reactors. (2) Coating. The coating can provide a protective layer for the zirconium alloy that can reduce oxidation and hydrogen pick-up. The protective coating prepared on the zirconium cladding tube can effectively increase safety margins of nuclear plants. In general, the mechanical properties, the adherence between the coating and the zirconium substrate, the stability under irradiation and self-healing are the main problems that need to be taken into account. (3) Irradiation-induced damage. During service in nuclear reactors, zirconium alloys are exposed to neutron irradiation. Neutron irradiation can affect microstructural evolution, and the mechanical and corrosion properties of zirconium alloys. Irradiation-induced damage is one of the most important factors affecting the lifetime of zirconium alloy components in reactors.
A new generation of reactors will offer higher fuel burn-up, higher efficiency and excellent safety of operation. The performance and high efficiency of these advanced reactors are linked to more severe service environments. New zirconium alloys with improved resistance to the environment of high temperature, high pressure, high corrosion and high radiation field are necessary.
Dr. Wen Qin
Manuscript Submission Information
Manuscripts should be submitted online at www.mdpi.com by registering and logging in to this website. Once you are registered, click here to go to the submission form. Manuscripts can be submitted until the deadline. All papers will be peer-reviewed. Accepted papers will be published continuously in the journal (as soon as accepted) and will be listed together on the special issue website. Research articles, review articles as well as short communications are invited. For planned papers, a title and short abstract (about 100 words) can be sent to the Editorial Office for announcement on this website.
Submitted manuscripts should not have been published previously, nor be under consideration for publication elsewhere (except conference proceedings papers). All manuscripts are thoroughly refereed through a single-blind peer-review process. A guide for authors and other relevant information for submission of manuscripts is available on the Instructions for Authors page. Metals is an international peer-reviewed open access monthly journal published by MDPI.
Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 1500 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.
- Zirconium alloys
- Mechanical properties
- Hydrogen embrittlement