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Hydrogenation behavior of Cr-coated laser beam welds of E110 zirconium alloy

  • Published:2022-11 Issue: Volume:570 Page:153980
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Kashkarov E.B.,Kudiiarov V.N.,Kurdyumov N.,Krinitcyn M.G.,Sidelev D.V.

Funder

Russian Science Foundation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference61 articles.

1. Zirconium alloys for supercritical water reactor applications: Challenges and possibilities;Motta;J. Nucl. Mater.,2007

2. The current status and prospects of production progress of Zr, Zr-base alloys and products made from them;Shikov;Fiz. Khim. Obrab. Mater.,2001

3. Ductile-to-brittle transition of oxidised zircaloy-4 and E110 claddings;Hózer;J. Nucl. Mater.,2008

4. Nuclear physical properties of zirconium alloys E110 and E635 under long-term neutron irradiation in VVER-1000 reactor;Blokhin;Inorg. Mater.,2012

5. Current status of materials development of nuclear fuel cladding tubes for light water reactors;Duan;Nucl. Eng. Des.,2017
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