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...
Main Authors: | , |
---|---|
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 |
id |
doaj-e6f72f6f0f2642509e3599b6830420ba |
---|---|
record_format |
Article |
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 |
work_keys_str_mv |
AT brunogonfiotti standalonecontainmentanalysisofthephebusfpttestswiththeastecandthemelcorcodesthefpt0test AT sandropaci standalonecontainmentanalysisofthephebusfpttestswiththeastecandthemelcorcodesthefpt0test |
_version_ |
1725258886820134912 |