Effect of Thermal Cycling of Zr-1%Nb Fuel Rod Claddings on Hydride Reorientation

Author:

Riedkina Ganna P.1ORCID,Krasnorutskyy Volodmyr S.1ORCID,Grytsyna Viktor M.1ORCID,Grudnitskii Vadym V.1ORCID

Affiliation:

1. “Nuclear Fuel Cycle” Science and Technology Establishment of National Science Center “Kharkiv Institute of Physics and Technology,” 1 Akademichna St., Kharkiv, 61108, UA

Publisher

ASTM International

Reference43 articles.

1. Extended Dry Storage of Used Nuclear Fuel: Technical Issues: A USA Perspective;McConnell;Nuclear Engineering and Technology,2011

2. Hydride Platelet Reorientation in Zircaloy Studied with Synchrotron Radiation Diffraction;Colas;Journal of ASTM International,2011

3. Radial-Hydride Embrittlement of High-Burnup Zircaloy-4 Fuel Cladding;Daum;Journal of Nuclear Science and Technology,2006

4. Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage;Aomi;Journal of ASTM International,2008

5. R. H. Jones Jr., Dry Storage Cask Inventory Assessment, FCRD-NFST-2014-000602, Rev. 2. (Washington, DC: U.S. Department of Energy, 2016).

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