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For: Journeau C, Aufore L, Berge L, Brayer C, Cassiaut-Louis N, Estre N, Payot F, Piluso P, Prele JC, Singh S, Zabiégo M, Pluyette E, Serre F, Teisseire B. Corium-Sodium and Corium-Water Fuel-Coolant-Interaction Experimental Programs for the PLINIUS2 Prototypic Corium Platform. NUCL TECHNOL 2018. [DOI: 10.1080/00295450.2018.1479580] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
Number Cited by Other Article(s)
1
Characterization of high-temperature nuclear fuel-coolant interactions through X-ray visualization and image processing. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107881] [Citation(s) in RCA: 6] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
2
Uršič M, Leskovar M. Investigation of challenges related to vapour explosion modelling in sodium. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110646] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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