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Science and Technology of Nuclear Installations
Volume 2017, Article ID 1450648, 25 pages
Research Article

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

Dipartimento di Ingegneria Civile e Industriale (DICI), University of Pisa, Largo Lucio Lazzarino 2, 56122 Pisa, Italy

Correspondence should be addressed to Bruno Gonfiotti; ti.ipinu.rof@ittoifnog.onurb

Received 13 May 2017; Accepted 21 August 2017; Published 5 December 2017

Academic Editor: Tomasz Kozlowski

Copyright © 2017 Bruno Gonfiotti and Sandro Paci. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


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.