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2. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors;E Rouesne;Journal of Nuclear Materials,2019
3. Behavior under LOCA conditions of enhanced accident tolerant chromium coated zircaloy-4 claddings;J.-C Brachet;Topfuel 2016-Light Water Reactor (LWR) Fuel Performance Meeting,2016
4. Behavior of chromium coated M5 claddings upon thermal ramp tests under internal pressure (loss-ofcoolant accident conditions);H Chung;Topfuel 2018-Light Water Reactor (LWR) Fuel Performance Meeting,1969