Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations

Author:

Suman Siddharth

Funder

Board of Research in Nuclear Sciences

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Hydrogen in zircaloy: mechanism and its impacts;Suman;Int. J. Hydrogen Energy,2015

2. Safety researches on LWR loss-of-coolant accident;Sato;J. Nucl. Sci. Technol.,1989

3. Influence of hydrogen content on the α/β phase transformation temperatures and on the thermal-mechanical behavior of zy-4, M4 (ZrSnFeV), and M5TM (ZrNbO) alloys during the first phase of LOCA transient;Brachet,2009

4. Effects of oxide and hydrogen on the behavior of Zircaloy-4 cladding during the loss of the coolant accident (LOCA);Kim;Nucl. Eng. Des.,2006

5. Failure-bearing capability of oxidized zircaloy-4 cladding under simulated loss-of-coolant condition;Uetsuka;J. Nucl. Sci. Technol.,1983

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