Open AccessRBMK thermohydraulic safety assessments using RELAP5/MOD3 codes
Author(s) -
G.V. Tsiklauri,
Bruce E. Schmitt
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/79081
Subject(s) - rbmk , nuclear engineering , core (optical fiber) , tube (container) , environmental science , coolant , pressurized water reactor , nuclear reactor , mechanics , materials science , engineering , mechanical engineering , physics , composite material
The capability of the RELAP5/MOD3 code to validate various transients encountered in RBMK reactor postulated accidents has been assessed. The assessment results include a loss of coolant accident at the inlet of the core pressure tube, the blockage of a pressure tube, and the pressure response of the core cavity to in core pressure tube ruptures. These assessments show that the RELAP5/MOD3 code can predict major phenomena during postulated accidents in the RBMK reactors