Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout

Author:

Guo Zehua,Dailey Ryan,Zhou Yukun,Sun Zhongning,Wang JunORCID,Corradini Michael L.

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference40 articles.

1. AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding;Bischoff;Nucl. Eng. Technol.,2018

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

3. High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process;Brachet;Corros. Sci.,2020

4. Brachet, J.C., Le Saux, M., Le Flem, M., Urvoy, S., Rouesne, E., Guilbert, T., Cobac, C., Lahogue, F., Rousselot, J., Tupin, M., Billaud, P., Hossepied, C., Schuster, F., Lomello, F., Billard, A., Velisa, G., Monsifrot, E., Bischoff, J., Ambard, A., 2015. On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRs fuel. Proc Top Fuel 2015, Zurich, Switzerland, 31-38.

5. Microstructure and high-temperature steam oxidation properties of thick Cr coatings prepared by magnetron sputtering for accident tolerant fuel claddings: The role of bias in the deposition process;Chen,2020

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