The document deals with the description of results obtained by the Relap5 code in the post-test simulation of the Loss of Feed Water (LOFW) experiment performed in the Pressurized Water Reactor (PWR) experimental simulator SPES installed at the Piacenza SIET Research Center in Italy. The Relap5 is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since more than a decade. The SPES is a 1/700 scale Integral Test Facility (ITF) simulating with full height, full pressure, full linear power a US type PWR, three-loop Westinghouse. The concerned test was selected as International Standard Problem 22 (ISP 22) 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 for issuing the final ‘comparison report’. This is called open post-test analysis: the comparison of about 60 calculated time trends with measured data allows an evaluation of the capabilities of the computer code and of the code user team in predicting the scenario of an accident. This is relevant for demonstrating the capabilities in evaluating safety margins of existing NPP, with main reference to PWR LOFW (in this case).
Post-test Analysis of Spes test SP-FW-02 (ISP 22) with Relap5/mod2 Code, OECD CSNI Final Workshop on ISP 22 - Pisa (I) July 2-4 1991
D'Auria F.
Co-primo
Supervision
;
1991-01-01
Abstract
The document deals with the description of results obtained by the Relap5 code in the post-test simulation of the Loss of Feed Water (LOFW) experiment performed in the Pressurized Water Reactor (PWR) experimental simulator SPES installed at the Piacenza SIET Research Center in Italy. The Relap5 is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since more than a decade. The SPES is a 1/700 scale Integral Test Facility (ITF) simulating with full height, full pressure, full linear power a US type PWR, three-loop Westinghouse. The concerned test was selected as International Standard Problem 22 (ISP 22) 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 for issuing the final ‘comparison report’. This is called open post-test analysis: the comparison of about 60 calculated time trends with measured data allows an evaluation of the capabilities of the computer code and of the code user team in predicting the scenario of an accident. This is relevant for demonstrating the capabilities in evaluating safety margins of existing NPP, with main reference to PWR LOFW (in this case).I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
