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
Accelerating Research
Robert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom
Address
John Eccles HouseRobert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom