KOHURT, P. (BNL), KALINICHENKO, S.D.; KROSHILIN, A.E.; KROSHILIN, V.E. & SMIRNOV, A.V. TWO-PHASE FLOW STUDIES IN NUCLEAR POWER PLANT PRIMARY CIRCUITS USING THE THREE-DIMENSIONAL THERMAL-HYDRAULIC CODE BAGIRA., article, June 4, 2006; (https://digital.library.unt.edu/ark:/67531/metadc892745/m1/1/: accessed April 18, 2024), University of North Texas Libraries, UNT Digital Library, digital.library.unt.edu; .

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