Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test

During the last 40 years, many studies have been carried out to investigate the different phenomena occurring during a Severe Accident (SA) in a Nuclear Power Plant (NPP). Such efforts have been supported by the execution of different experimental campaigns, and the integral Phébus FP tests were pro...

Full description

Bibliographic Details
Main Authors: Bruno Gonfiotti, Sandro Paci
Format: Article
Language:English
Published: Elsevier 2018-03-01
Series:Heliyon
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2405844017328347
id doaj-94bf6344d3544e97b7e5784d4cbe37cd
record_format Article
spelling doaj-94bf6344d3544e97b7e5784d4cbe37cd2020-11-25T03:46:41ZengElsevierHeliyon2405-84402018-03-0143e00553Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 testBruno Gonfiotti0Sandro Paci1Corresponding author.; University of Pisa, Dipartimento di Ingegneria Civile e Industriale (DICI), Largo Luciano Lazzarino 2, 56122, Pisa, ItalyUniversity of Pisa, Dipartimento di Ingegneria Civile e Industriale (DICI), Largo Luciano Lazzarino 2, 56122, Pisa, ItalyDuring the last 40 years, many studies have been carried out to investigate the different phenomena occurring during a Severe Accident (SA) in a Nuclear Power Plant (NPP). Such efforts have been supported by the execution of different experimental campaigns, and the integral Phébus FP tests were probably some of the most important experiments in this field. In these tests, the degradation of a Pressurized Water Reactor (PWR) fuel bundle was investigated employing different control rod materials and burn-up levels in strongly or weakly oxidizing conditions. From the findings on these and previous tests, numerical codes such as ASTEC and MELCOR have been developed to analyze the evolution of a SA in real NPPs. After the termination of the Phébus FP campaign, these two codes have been furthermore improved to implement the more recent findings coming from different experimental campaigns. Therefore, continuous verification and validation is still necessary to check that the new improvements introduced in such codes allow also a better prediction of these Phébus tests. The aim of the present work is to re-analyze the Phébus FPT-2 test employing the updated ASTEC and MELCOR code versions. The analysis focuses on the stand-alone containment aspects of this test, and three different spatial nodalizations of the containment vessel (CV) have been developed. The paper summarizes the main thermal-hydraulic results and presents different sensitivity analyses carried out on the aerosols and fission products (FP) behavior. When possible, a comparison among the results obtained during this work and by different authors in previous work is also performed. This paper is part of a series of publications covering the four Phébus FP tests using a PWR fuel bundle: FPT-0, FPT-1, FPT-2, and FPT-3, excluding the FPT-4 one, related to the study of the release of low-volatility FP and transuranic elements from a debris bed and a pool of melted fuel.http://www.sciencedirect.com/science/article/pii/S2405844017328347Safety engineeringNuclear engineering
collection DOAJ
language English
format Article
sources DOAJ
author Bruno Gonfiotti
Sandro Paci
spellingShingle Bruno Gonfiotti
Sandro Paci
Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test
Heliyon
Safety engineering
Nuclear engineering
author_facet Bruno Gonfiotti
Sandro Paci
author_sort Bruno Gonfiotti
title Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test
title_short Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test
title_full Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test
title_fullStr Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test
title_full_unstemmed Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test
title_sort stand-alone containment analysis of phébus fpt tests with astec and melcor codes: the fpt-2 test
publisher Elsevier
series Heliyon
issn 2405-8440
publishDate 2018-03-01
description During the last 40 years, many studies have been carried out to investigate the different phenomena occurring during a Severe Accident (SA) in a Nuclear Power Plant (NPP). Such efforts have been supported by the execution of different experimental campaigns, and the integral Phébus FP tests were probably some of the most important experiments in this field. In these tests, the degradation of a Pressurized Water Reactor (PWR) fuel bundle was investigated employing different control rod materials and burn-up levels in strongly or weakly oxidizing conditions. From the findings on these and previous tests, numerical codes such as ASTEC and MELCOR have been developed to analyze the evolution of a SA in real NPPs. After the termination of the Phébus FP campaign, these two codes have been furthermore improved to implement the more recent findings coming from different experimental campaigns. Therefore, continuous verification and validation is still necessary to check that the new improvements introduced in such codes allow also a better prediction of these Phébus tests. The aim of the present work is to re-analyze the Phébus FPT-2 test employing the updated ASTEC and MELCOR code versions. The analysis focuses on the stand-alone containment aspects of this test, and three different spatial nodalizations of the containment vessel (CV) have been developed. The paper summarizes the main thermal-hydraulic results and presents different sensitivity analyses carried out on the aerosols and fission products (FP) behavior. When possible, a comparison among the results obtained during this work and by different authors in previous work is also performed. This paper is part of a series of publications covering the four Phébus FP tests using a PWR fuel bundle: FPT-0, FPT-1, FPT-2, and FPT-3, excluding the FPT-4 one, related to the study of the release of low-volatility FP and transuranic elements from a debris bed and a pool of melted fuel.
topic Safety engineering
Nuclear engineering
url http://www.sciencedirect.com/science/article/pii/S2405844017328347
work_keys_str_mv AT brunogonfiotti standalonecontainmentanalysisofphebusfpttestswithastecandmelcorcodesthefpt2test
AT sandropaci standalonecontainmentanalysisofphebusfpttestswithastecandmelcorcodesthefpt2test
_version_ 1724504874491576320