The document deals with the description of results obtained by the Relap5 code in the post-test simulation of the blowdown-containment pressurization experiment performed in the Simplified Boiling Water Reactor (SBWR) experimental simulator PANDA installed at the PSI Research Center in Villingen-Wurenlingen - Switzerland. The Relap5 is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since about two decades. The PANDA is a large scale Integral Test Facility (ITF) simulating a US (General Electric) type SBWR. The concerned test was selected as International Standard Problem 42 (ISP 42) by OECD/NEA/CSNI (Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installations). The document describes the results of the post-test calculation submitted (by UNIPI) to PSI (Swiss Nuclear energy Research Institute) after the execution of the test and following the submittal of pre-test analysis. This is relevant for demonstrating the capabilities in evaluating safety margins of existing NPP, with main reference to innovative reactors (in this case).
Analysis of OECD/CSNI ISP-42 Panda Experiment by Relap5/mod3.2 Code
D'Auria F.
Co-primo
Methodology
;
2001-01-01
Abstract
The document deals with the description of results obtained by the Relap5 code in the post-test simulation of the blowdown-containment pressurization experiment performed in the Simplified Boiling Water Reactor (SBWR) experimental simulator PANDA installed at the PSI Research Center in Villingen-Wurenlingen - Switzerland. The Relap5 is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since about two decades. The PANDA is a large scale Integral Test Facility (ITF) simulating a US (General Electric) type SBWR. The concerned test was selected as International Standard Problem 42 (ISP 42) by OECD/NEA/CSNI (Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installations). The document describes the results of the post-test calculation submitted (by UNIPI) to PSI (Swiss Nuclear energy Research Institute) after the execution of the test and following the submittal of pre-test analysis. This is relevant for demonstrating the capabilities in evaluating safety margins of existing NPP, with main reference to innovative reactors (in this case).I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
