General Description of the PACTEL Test Facility

摘要

The PACTEL is a test facility designed to model the thermal-hydraulic behaviors211u001eof the Soviet-designed VVER-440 pressurized water reactors currently in use in 211u001eFinland. This report describes some of the affects of the smaller hydraulic 211u001ediameters on the thermal-hydraulic characteristics of the PACTEL. This report 211u001ealso discussed the thermal-hydraulic affects of larger secondary-side volumes. 211u001eAssessing thermal-hydraulic computer codes used for the safety analyses of 211u001enuclear power plants is the final goal of the PACTEL experiment programs. The 211u001ereport supplies the physical data on the PACTEL that analysts need to prepare 211u001etheir code models. It describes the PACTEL instrumentation and data acquisition 211u001esystem. The report also lists the experiments conducted prior to publishing and 211u001esummarizes each experiment procedure.