SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission product behaviour

Giuli, M. Di; Haste, T.; Biehler, R.; Bosland, L.; Herranz, L.E.; Fontanet, Joan; Beuzet, E.; Torkhani, Mohamed; Davidovich, N.; Klein-Heßling, W.; Weber, Sebastian; Dickinson, S.; Horváth, Gábor; Kruse, P.J.; Koch, Marco K.; Paci, Sandro; Salay, Michael; Buján, Antonio Fernández de; Ivanov, Ivan; Kalychev, P.; Kim, S.B.; Morandi, S.; Corno, Ada Del; Kotouč, Miroslav; Dienstbier, J.; Kim, H.-C.

doi:10.1016/j.anucene.2016.01.046

Cited by 10 publications

(16 citation statements)

References 34 publications

(22 reference statements)

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“…The aim of the work is to investigate the main parameters influencing the FPs behavior inside the containment during the four main phases of the test (degradation, aerosol, washing, and chemistry phases). Different previous analyses (for the full-plant or the standalone containment) have employed too complex or too coarse nodalizations [10][11][12][13][14][15], not able to catch the main thermalhydraulics or aerosol phenomena, or to be employed for full-plant analysis. For this purpose, three different spatial nodalizations of the Phébus containment vessel have been developed to show that too simple nodalizations are not able to simulate the thermal-hydraulic transient.…”

Section: Introductionmentioning

confidence: 99%

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

Bruno

Paci

2017

Science and Technology of Nuclear Installations

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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.

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Section: Introductionmentioning

confidence: 99%

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

Bruno

Paci

2017

Science and Technology of Nuclear Installations

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“…As an example in Fig. 10, the comparison of ASTEC Phébus FPT3 calculations with the experimental data show that the evolution of bundle temperatures during the core degradation phase is well captured, as are that for the hydrogen production (experimental uncertainty 5% with one standard deviation), as demonstrated also in the FPT3 benchmark (Di Giuli et al, 2014).…”

Section: Validation Versus Experimentsmentioning

confidence: 78%

“…A benchmark exercise has also been completed on the Phébus FPT3 integral test that allowed to assess progress of simulation codes since ISP46 on FPT1 and to confirm the importance of the on-going research programs (Di Giuli et al, 2014). As for source term, the benchmark emphasized that presently estimates are overwhelmed by uncertainties in chemistry that, finally, resulted in major difficulties to predict gaseous iodine fraction in containment within an order of magnitude.…”

Section: Source Termmentioning

confidence: 99%

Recent severe accident research synthesis of the major outcomes from the SARNET network

Dorsselaere

Auvinen

Beraha

et al. 2015

Nuclear Engineering and Design

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The SARNET network (Severe Accident Research NETwork of excellence), co-funded by the European Commission from 2004 to 2013, has allowed to significantly improve the knowledge on severe accidents and to disseminate it through courses and ERMSAR conferences. The major investigated topics, involving more than 250 researchers from 22 countries, were in- and ex-vessel corium/debris coolability, molten-core–concrete-interaction, steam explosion, hydrogen combustion and mitigation in containment, impact of oxidising conditions on source term, and iodine chemistry. The ranking of the high priority issues was updated to account for the results of recent international research and for the impact of Fukushima nuclear accidents in Japan. In addition, the ASTEC integral code was further developed to capitalize the new knowledge. The network has reached self-sustainability by integration in mid-2013 into the NUGENIA Association. The main activities and outcomes of the network are presented

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“…The FPT3 benchmark was well supported, with participation from 16 organisations in 11 countries, using 8 different codes, giving a good overview of the capability of source term (ST) modelling [7]. It followed a similar exercise, OECD/NEA/ISP-46 [8], on FPT1 that used steam-rich conditions with an Ag/In/Cd control rod.…”

Section: Phébus Fpt3mentioning

confidence: 99%

“…More reliable assessment of the iodine models is obtained using stand-alone calculations with iodine source input based on the test data. Example results are given in Figure 1 while a fuller summary is given in [7]. In the stand-alone calculations, iodine deposition on painted surfaces, 54% containment inventory (c.i.…”

Section: Phébus Fpt3mentioning

confidence: 99%

Iodine Benchmarks in the SARNET Network of Excellence

Haste

Giuli

Weber

et al. 2016

Journal of Nuclear Engineering and Radiation Science

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Accurate calculation of iodine behavior in the containment is very important in determining the potential radioactive release to the environment in light water reactor severe accidents (SAs). Of particular significance is the behavior of gas phase iodine, particularly organic iodine, which is difficult to remove by filtration, e.g., in containment venting systems. Iodine behavior is closely linked with the containment thermal hydraulics, which have a major influence on the distribution of iodine throughout the containment atmosphere and sump. In the European 7th Framework SARNET project, European Commission (EC) cofunded from 2007 to 2013, SA modeling code capability was assessed through two integral benchmarks. In the first, the basis was the German THAI Iod-11/12 tests, where molecular iodine transport with atmospheric flows and iodine interactions with steel surfaces were emphasized. In the second, data from the international Phébus FPT3 test were used, where all aspects of SAs were studied from core degradation, fission product (FP) release, circuit transport/deposition, and containment behavior using realistic FP sources. Thermal hydraulics in the containment were simpler, being well-mixed, and radiolytic interactions of iodine, e.g., with painted surfaces, were studied. These interactions may be an important source of organic iodine in the containment atmosphere. The two benchmarks are thus complementary. In the FPT3 exercise, the calculations could predict the containment thermal hydraulic conditions fairly well. For the more detailed data from THAI, differences were noted for atmospheric flows and relative humidities, outside experimental uncertainties, affecting iodine behavior. The FPT3 iodine results themselves showed a spread in calculated results outside data uncertainties, indicating the need for model improvements in this area, e.g., for radiolytic interaction of iodine with paint. Experimental programs to generate the necessary data needed for code improvement have been recently completed, e.g., in the OECD/THAI, THAI2, BIP, and BIP2 projects, or are in progress, in OECD/STEM and EC/PASSAM. When model improvements have been made, repeat benchmarks are planned to check progress toward code convergence with experimental data, e.g., under the aegis of the new NUGENIA association of which SARNET now forms a part.

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SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission product behaviour

Cited by 10 publications

References 34 publications

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

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

Recent severe accident research synthesis of the major outcomes from the SARNET network

Iodine Benchmarks in the SARNET Network of Excellence

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