Study of the material release during PHÉBUS FPT-1 bundle phase with MELCOR 2.2

Darnowski, Piotr; Włostowski, Mateusz; Stępień, Michał; Niewiński, Grzegorz

doi:10.1016/j.anucene.2020.107700

Cited by 10 publications

(15 citation statements)

References 19 publications

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“…The core was modelled with a single thermal-hydraulic control volume (CV). This approach was able to predict the proper mass of hydrogen as discussed in previous works [29].…”

Section: Methodology 21 Phébus Fpt-1 Modelmentioning

confidence: 67%

“…The Phébus FPT-1 input deck was developed during previous research [28,29] and updated to be used with the recent MELCOR 2.2. 18.…”

Section: Methodology 21 Phébus Fpt-1 Modelmentioning

confidence: 99%

“…The model details are presented and discussed in [29] and are not reproduced in this article. Modifications were introduced, including modelling details for uncertainty parameters described in the following chapter and minor changes in the interactive model setup for eutectic reactions modelled with an MP_PRC card.…”

Section: Methodology 21 Phébus Fpt-1 Modelmentioning

confidence: 99%

“…HTCs for ZrO 2 and UO 2 were modified and equal to 20,000 W•m −2 •K −1 and 30,000 W•m −2 •K −1 , respectively. In our previous studies ( [28,29]), we assumed a candling heat transfer of 20,000 W•m −2 •K −1 for metallic Zr (COR_CHT (1)), and the uncertain parameter was the same as this modified value. It was a mistake; the ZrO 2 (COR_CHT (2)) should have been modified instead.…”

Section: Fractional Dissolution Of Materials-fuozr and Fsxssmentioning

confidence: 99%

“…It is defined in the TMLT field in the MP_PRC card used to define new materials and model in the COR_MAT card. In previous research [29] for FPT-1, we applied different tables based on the MP_PRTF card; here, it was simplified with MP_PRC as discussed in [57].…”

Section: Time-at-temperature Model-iroddamagementioning

confidence: 99%

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Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2

2021

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In this study, uncertainty and sensitivity analyses were performed with MELCOR 2.2.18 to study the hydrogen generation (figure-of-merit (FoM)) during the in-vessel phase of a severe accident in a light water reactor. The focus of this work was laid on a large generation-III pressurized water reactor (PWR) and a double-ended hot leg (HL) large break loss of coolant accident (LB-LOCA) without a safety injection (SI). The FPT-1 Phebus integral experiment emulating LOCA was studied, where the experiment outcomes were applied for the plant scale modelling. The best estimate calculations were supplemented with an uncertainty analysis (UA) based on 400 input-decks and Latin hypercube sampling (LHS). Additionally, the sensitivity analysis (SA) utilizing the linear regression and linear and rank correlation coefficients was performed. The study was prepared with a new open-source MELCOR sensitivity and uncertainty tool (MelSUA), which was supplemented with this work. The FPT-1 best-estimate model results were within the 10% experimental uncertainty band for the final FoM. It was shown that the hydrogen generation uncertainties in PWR were similar to the FPT-1, with the 95% percentile being covered inside a ~50% band and the 50% percentile inside a ~25% band around the FoM median. Two different power profiles for PWR were compared, indicating its impact on the uncertainty but also on the sensitivity results. Despite a similar setup, different uncertainty parameters impacted FoM, showing the difference between scales but also a significant impact of boundary conditions on the sensitivity analysis.

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“…The core was modelled with a single thermal-hydraulic control volume (CV). This approach was able to predict the proper mass of hydrogen as discussed in previous works [29].…”

Section: Methodology 21 Phébus Fpt-1 Modelmentioning

confidence: 67%

“…The Phébus FPT-1 input deck was developed during previous research [28,29] and updated to be used with the recent MELCOR 2.2. 18.…”

Section: Methodology 21 Phébus Fpt-1 Modelmentioning

confidence: 99%

Section: Methodology 21 Phébus Fpt-1 Modelmentioning

confidence: 99%

Section: Fractional Dissolution Of Materials-fuozr and Fsxssmentioning

confidence: 99%

Section: Time-at-temperature Model-iroddamagementioning

confidence: 99%

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Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2

2021

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Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident

Zhao

Zou²,

et al. 2022

Intl J of Energy Research

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Summary A simulation calculation model in the case of a severe accident such as a loss of coolant accident (LOCA) was established and calculated by MELCOR code in a marine pressurized water reactor. The effects of severe accidents on the hydrogen source term, release of the radionuclide source term, and the accident process were investigated, and the radiation consequences were analyzed. LOCA sensitivity analysis was conducted with different break sizes; the release and diffusion of source terms were analyzed. The results indicated that the hydrogen yield in the reactor core was dependent on the temperature, and on the residual water in the reactor core, which has no direct relationship with the break size. The break size directly affected the accident progression. However, when the break exceeded a certain size, it did not affect the LOCA process. The break size may not change to change the release amount and migration rule of radionuclides such as Xe and I, and the fission product CsI, as final containment is in dynamic equilibrium in LOCA conditions. The contents of fission products released into the containment vessel, major loop, cavity, and the environment are sensitive to the break size. However, no special correlation is observed between the amount released and the break size. Highlights The hydrogen yield in the reactor core was dependent on the temperature, and on the residual water in the reactor core, which has no direct relationship with the break size. The break size may not change to change the release amount and migration rule of radionuclides such as Xe, I, and CsI, as final containment is in dynamic equilibrium in LOCA conditions. No particular correlation is observed between the amount of radionuclide released and the break size.

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Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project

Mascari,

Bersano,

Massone

et al. 2024

Annals of Nuclear Energy

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Study of the material release during PHÉBUS FPT-1 bundle phase with MELCOR 2.2

Cited by 10 publications

References 19 publications

Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2

Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2

Effect analysis of break size on source term release and radioactive consequences of marine nuclear reactor during loss of coolant accident

Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project

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