The aim of the this study is to perform an evaluation of the behaviour of a single RBMK reactor core fuel channel focusing on the fuel clad and the Pressure Tube, in case of a flow blockage accident. The tools used were the RELAP5 and FRAP code. The RBMK channel, the graphite stack and the He-N2 gap were modelled with the RELAP5 code; the thermo-mechanical fuel rod behaviour was studied by FRAP code. Some cases were analyzed considering different values of coolant flow reduction at different values of the channel power in order to demonstrate if the break of the pressure tube and the failure of fuel clad occur. A failure map was drawn identifying safe operational zones for the Pressure Tube and the fuel clad.
Analysis of flow blockage of a single RBMK channel
D'AURIA, FRANCESCO SAVERIO
2005-01-01
Abstract
The aim of the this study is to perform an evaluation of the behaviour of a single RBMK reactor core fuel channel focusing on the fuel clad and the Pressure Tube, in case of a flow blockage accident. The tools used were the RELAP5 and FRAP code. The RBMK channel, the graphite stack and the He-N2 gap were modelled with the RELAP5 code; the thermo-mechanical fuel rod behaviour was studied by FRAP code. Some cases were analyzed considering different values of coolant flow reduction at different values of the channel power in order to demonstrate if the break of the pressure tube and the failure of fuel clad occur. A failure map was drawn identifying safe operational zones for the Pressure Tube and the fuel clad.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
