RELAP5/MOD3.3 Assessment against New PMK Experiments. International Agreement Report

摘要

The PMK-2 facility is a scaled down model of the VVER-440/213 and it had been primarily designed for investigation of small-break loss of coolant accidents (SBLOCA) and transient processes of this type of NPP. Nowadays the facility is also widely used for assessment of advanced computer code, that are used for safety analysis in VVER-operating countries. One of the most important and world-widespread computer codes is the RELAP5 code. In the Czech Republic, the RELAP5 is installed under agreement between US NRC and Czech regulatory body (SONS). The main user of the code is the Nuclear Research Institute (NRI, UJV) Rez, where the code is widely assessed and applied to NPP safety analyses. The tests used in this report for assessment of RELAP5/MOD3.3 computer code are mediumbreak LOCA accidents without HPSI and with operator interventions (secondary bleed, primary bleed).