Abstract
In 1993 the International Atomic Energy Agency Standard Problem Exercise no.4 (IAEA-SPE-4), a small break LOCA scenario simulation with no high pressure injection system available, was performed on the PMK-2 integral test facility in Budapest. Later, in 1994, another SB LOCA experiment was performed. The analyses of the PMK-2 facility response, a model of WER-440 nuclear power plant, have been performed using the MOD3.2.1.2 version of the RELAP5 thermal-hydraulic computer code.
Volume Subject Area:
CFD and Thermal Hydraulics Analysis in Nuclear Reactors
This content is only available via PDF.
Copyright © 1998 by The American Society of Mechanical Engineers
You do not currently have access to this content.
