In the frame of WP4 of SARNET European Project the LOFT LP-FP2 experiment has been analysed with ASTEC V1.2.1 for code validation purposes. The LOFT input deck provided by IRSN has been improved according to standard PWR reactor applications and the experience gained in the analysis of Bethsy experiments. The calculation results have been compared with experimental data in order to assess the ability of ASTEC code for simulating thermal-hydraulic behaviour, core degradation, hydrogen generation and fission product release which might occur during a severe accident in a PWR. Furthermore, the ASTEC results have been compared with the results of ICARE/CATHARE code. Finally, some sensitivity studies have been performed to evaluate the impact of uncertain key parameters on code response.

Analysis of the OECD LOFT Fission Product Experiment LP-FP-2 with ASTEC VI .2.1 Code

Bandini, G.
2006

Abstract

In the frame of WP4 of SARNET European Project the LOFT LP-FP2 experiment has been analysed with ASTEC V1.2.1 for code validation purposes. The LOFT input deck provided by IRSN has been improved according to standard PWR reactor applications and the experience gained in the analysis of Bethsy experiments. The calculation results have been compared with experimental data in order to assess the ability of ASTEC code for simulating thermal-hydraulic behaviour, core degradation, hydrogen generation and fission product release which might occur during a severe accident in a PWR. Furthermore, the ASTEC results have been compared with the results of ICARE/CATHARE code. Finally, some sensitivity studies have been performed to evaluate the impact of uncertain key parameters on code response.
Rapporto tecnico;Reattori nucleari ad acqua;Sicurezza nucleare;Analisi incidentale
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/5282
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