Estimation of ring tensile properties of steam oxidized Zircaloy-4 fuel cladding under simulated LOCA condition

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Date

2017

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Abstract

Description

Keywords

Loss of coolant accident, Steam oxidation, Oxide layer, alpha-Zr(O) layer, Cladding embrittlement, Ring tension test

Source

Journal of Nuclear Materials, 2017. Vol. 493: pp. 460-470

URI

http://hdl.handle.net/123456789/15434

Collections

2017