Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test

The integral Phébus tests were probably one of the most important experimental campaigns performed to investigate the progression of severe accidents in light water reactors. In these tests, the degradation of a PWR fuel bundle was investigated employing different control rod materials and burn-up l...

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Main Authors: Bruno Gonfiotti, Sandro Paci
Format: Article
Language:English
Published: Hindawi Limited 2017-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2017/1450648
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spelling doaj-e6f72f6f0f2642509e3599b6830420ba2020-11-25T00:47:44ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/14506481450648Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 TestBruno Gonfiotti0Sandro Paci1Dipartimento di Ingegneria Civile e Industriale (DICI), University of Pisa, Largo Lucio Lazzarino 2, 56122 Pisa, ItalyDipartimento di Ingegneria Civile e Industriale (DICI), University of Pisa, Largo Lucio Lazzarino 2, 56122 Pisa, ItalyThe integral Phébus tests were probably one of the most important experimental campaigns performed to investigate the progression of severe accidents in light water reactors. In these tests, the degradation of a PWR fuel bundle was investigated employing different control rod materials and burn-up levels in strongly or weakly oxidizing conditions. From the results of such tests, numerical codes such as ASTEC and MELCOR have been developed to describe the evolution of a severe accident. After the termination of the experimental Phébus campaign, these two codes were furthermore expanded. Therefore, the aim of the present work is to reanalyze the first Phébus test (FPT-0) employing the updated ASTEC and MELCOR versions to ensure that the new improvements introduced in such codes allow also a better prediction of these Phébus tests. The analysis focuses on the stand-alone containment aspects of this test, and the paper summarizes the main thermal-hydraulic results and presents different sensitivity analyses carried out on the aerosols and fission products behavior. This paper is part of a series of publications covering the four executed Phébus tests employing a solid PWR fuel bundle: FPT-0, FPT-1, FPT-2, and FPT-3.http://dx.doi.org/10.1155/2017/1450648
collection DOAJ
language English
format Article
sources DOAJ
author Bruno Gonfiotti
Sandro Paci
spellingShingle Bruno Gonfiotti
Sandro Paci
Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
Science and Technology of Nuclear Installations
author_facet Bruno Gonfiotti
Sandro Paci
author_sort Bruno Gonfiotti
title Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
title_short Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
title_full Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
title_fullStr Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
title_full_unstemmed Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes: The FPT-0 Test
title_sort stand-alone containment analysis of the phébus fpt tests with the astec and the melcor codes: the fpt-0 test
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2017-01-01
description The integral Phébus tests were probably one of the most important experimental campaigns performed to investigate the progression of severe accidents in light water reactors. In these tests, the degradation of a PWR fuel bundle was investigated employing different control rod materials and burn-up levels in strongly or weakly oxidizing conditions. From the results of such tests, numerical codes such as ASTEC and MELCOR have been developed to describe the evolution of a severe accident. After the termination of the experimental Phébus campaign, these two codes were furthermore expanded. Therefore, the aim of the present work is to reanalyze the first Phébus test (FPT-0) employing the updated ASTEC and MELCOR versions to ensure that the new improvements introduced in such codes allow also a better prediction of these Phébus tests. The analysis focuses on the stand-alone containment aspects of this test, and the paper summarizes the main thermal-hydraulic results and presents different sensitivity analyses carried out on the aerosols and fission products behavior. This paper is part of a series of publications covering the four executed Phébus tests employing a solid PWR fuel bundle: FPT-0, FPT-1, FPT-2, and FPT-3.
url http://dx.doi.org/10.1155/2017/1450648
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AT sandropaci standalonecontainmentanalysisofthephebusfpttestswiththeastecandthemelcorcodesthefpt0test
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