Analysis of the water flow through the simplified central tube of the VVER 440 nuclear reactor fuel assembly
Author(s) -
Zdenko Závodný,
Jozef Bereznai,
František Urban
Publication year - 2016
Publication title -
aip conference proceedings
Language(s) - English
Resource type - Conference proceedings
eISSN - 1551-7616
pISSN - 0094-243X
DOI - 10.1063/1.4963053
Subject(s) - thermocouple , coolant , vver , nuclear engineering , computational fluid dynamics , nuclear reactor , flow (mathematics) , materials science , tube (container) , mechanics , environmental science , mechanical engineering , engineering , physics , composite material
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