Zirconium Alloys

A special issue of Metals (ISSN 2075-4701).

Deadline for manuscript submissions: closed (30 April 2018) | Viewed by 43866

Special Issue Editor


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Guest Editor
Department of Mechanical Engineering, University of Saskatchewan, Saskatoon, Canada

Special Issue Information

Dear Colleagues,

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
Guest Editor

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Keywords

  • Zirconium alloys
  • Mechanical properties
  • Corrosion
  • Oxidation
  • Hydrogen embrittlement
  • Hydride
  • Coating
  • Irradiation
  • Defects

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Published Papers (8 papers)

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2 pages, 144 KiB  
Editorial
Improvement and Application of Zirconium Alloys
Metals 2018, 8(10), 794; https://doi.org/10.3390/met8100794 - 4 Oct 2018
10 pages, 3081 KiB  
Article
Effects of Cold Swaging on Mechanical Properties and Magnetic Susceptibility of the Zr–1Mo Alloy
Metals 2018, 8(6), 454; https://doi.org/10.3390/met8060454 - 13 Jun 2018
9 pages, 11323 KiB  
Article
Phase Diagram of near Equiatomic Zr-Pd Alloy
Metals 2018, 8(5), 366; https://doi.org/10.3390/met8050366 - 21 May 2018
14 pages, 2146 KiB  
Article
Thermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings
Metals 2018, 8(1), 65; https://doi.org/10.3390/met8010065 - 18 Jan 2018
16 pages, 27095 KiB  
Article
Oxidation Behavior of Zr–1Nb Corroded in Air at 400 °C after Plasma Immersion Titanium Implantation
Metals 2018, 8(1), 27; https://doi.org/10.3390/met8010027 - 2 Jan 2018
14 pages, 4904 KiB  
Article
Fabrication and Characterization of a Low Magnetic Zr-1Mo Alloy by Powder Bed Fusion Using a Fiber Laser
Metals 2017, 7(11), 501; https://doi.org/10.3390/met7110501 - 13 Nov 2017
15 pages, 10186 KiB  
Article
Precipitate Stability in a Zr–2.5Nb–0.5Cu Alloy under Heavy Ion Irradiation
Metals 2017, 7(8), 287; https://doi.org/10.3390/met7080287 - 27 Jul 2017
10 pages, 4440 KiB  
Article
New Low-Sn Zr Cladding Alloys with Excellent Autoclave Corrosion Resistance and High Strength
Metals 2017, 7(4), 144; https://doi.org/10.3390/met7040144 - 19 Apr 2017
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