The document deals with the description of results obtained by the Cathare code in the new post-test’ of experiment F1.2 performed in the Pressurized Water Reactor (PWR) experimental simulator PKL installed at the Erlangen AREVA Research Center in Germany. The Cathare is the well-known computer code developed by CEA (Commissariat a l’Energie Atomique) in France in a cooperation with AREVA and EDF: the code is in use at UNIPI since about two decades. The PKL loop is an Integral Test Facility (ITF) simulating with full height, reduced pressure, full linear power a German 4-loop KWU-Siemens PWR. The PKL has four loops. The concerned test is part of a series of a dozen experiments performed in the framework of an Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installations (OECD/NEA/CSNI) project where University of Pisa is special member. The concerned experiment deals with Accident Management procedures applicable to Nuclear Power Plants. Attention is given in the document to nodalization qualification, namely based on new pressure drop data made available by experimentalists (AREVA in Germany).
Pressure Drops & Heat Losses in PKL-III Nodalization and Updated Analysis of Test PKL F1.2 by Cathare 2V2.5
D’Auria F.
Co-primo
Conceptualization
;
2008-01-01
Abstract
The document deals with the description of results obtained by the Cathare code in the new post-test’ of experiment F1.2 performed in the Pressurized Water Reactor (PWR) experimental simulator PKL installed at the Erlangen AREVA Research Center in Germany. The Cathare is the well-known computer code developed by CEA (Commissariat a l’Energie Atomique) in France in a cooperation with AREVA and EDF: the code is in use at UNIPI since about two decades. The PKL loop is an Integral Test Facility (ITF) simulating with full height, reduced pressure, full linear power a German 4-loop KWU-Siemens PWR. The PKL has four loops. The concerned test is part of a series of a dozen experiments performed in the framework of an Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installations (OECD/NEA/CSNI) project where University of Pisa is special member. The concerned experiment deals with Accident Management procedures applicable to Nuclear Power Plants. Attention is given in the document to nodalization qualification, namely based on new pressure drop data made available by experimentalists (AREVA in Germany).I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
