Effects of internal pressure and heating rate on the burst behaviors of Cr-coated cladding during simulated LOCA testing

Author:

Duan Zhengang,Yuan Bo,Wen Qinglong,Zhang Ruiqian,Chen Kang

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Reference21 articles.

1. Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing;Bell;J. Nucl. Mater.,2022

2. Brachet, J.-C., Le Saux, M., Lezaud-Chaillioux, V., Dumerval, M., Houmaire, Q., Lomello, F., Schuster, F., Monsifrot, E., Bischoff, J., Pouillier, E., 2016. Behavior under LOCA conditions of enhanced accident tolerant chromium coated zircaloy-4 claddings, Topfuel 2016-Light Water Reactor (LWR) Fuel Performance Meeting.

3. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors;Brachet;J. Nucl. Mater.,2019

4. Deformation Characteristics of Zircaloy Cladding In Vacuum And Steam Under Transient-Heating Conditions: Summary Report.[PWR; BWR];Chung,1978

5. Research progress on Cr coated zirconium alloy cladding for accident resistant fuel;Duan;Nucl. Technol.,2022

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