Uncertainty &amp; sensitivity analyses for LOCA simulation of PHEBUS experiment FPT-1 using a modified SUNSET code

Foad, Basma; Hassan, Mohga; Takeda, Takeshi

doi:10.1016/j.anucene.2020.107575

Cited by 4 publications

(4 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…We observed that using relatively simple and standard statistical tools for correlations (linear regression with Spearman or Pearson) do not provide conclusive answers about sources of uncertainty. These methods are very popular and were used by several researchers (e.g., [6,9]). It is difficult to indicate the main source of the observed variation in the final FoM.…”

Section: Discussionmentioning

confidence: 99%

“…Other plant details were also modelled, including the mai steam line with safety valves, the pressurizer with safety valves and accident valves, th The COR package model has nineteen axial levels and six rings. The active core region has twelve axial levels (7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18) and one non-active fuel level above and below the active core (6 and 19). The core support plate is modelled by level 5, and the levels below are part of the lower plenum.…”

Section: Gen-iii Pwr Modelmentioning

confidence: 99%

“…After the Fukushima Daiichi accident, much attention was paid to study the hydrogen production process in all LWR reactors. Recently, several studies were published about the in-vessel progression and the hydrogen production during severe accidents, including analytical case studies, uncertainty studies, and sensitivity studies or crosswalks with different severe accident codes, e.g., [5][6][7][8][9][10][11][12][13]. A single severe accident integral code run provides deterministic results, which has to be treated with a large margin of confidence.…”

Section: Introduction 1hydrogen During a Severe Accidentmentioning

confidence: 99%

See 2 more Smart Citations

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

2021

View full text Add to dashboard Cite

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.

show abstract

Section: Discussionmentioning

confidence: 99%

Section: Gen-iii Pwr Modelmentioning

confidence: 99%

Section: Introduction 1hydrogen During a Severe Accidentmentioning

confidence: 99%

See 1 more Smart Citation

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

2021

View full text Add to dashboard Cite

show abstract

“…The work presented here is a first approach to the UQ analysis in the MUSA project. The calculations were performed based on the Phébus FPT-1 experiment, which is a base for numerous similar investigations (Elsalamouny and Kaliatka, 2021) (Foad et al, 2020).…”

Section: Introductionmentioning

confidence: 99%

Parametric Melcor 2.2 Sensitivity and Uncertainty Study with a Focus on Aerosols, Based on Phébus Test Fpt1

Malicki¹,

Lind²

2022

SSRN Journal

View full text Add to dashboard Cite

Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1

Malicki

Lind

2023

Progress in Nuclear Energy

View full text Add to dashboard Cite

Uncertainty & sensitivity analyses for LOCA simulation of PHEBUS experiment FPT-1 using a modified SUNSET code

Cited by 4 publications

References 7 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

Parametric Melcor 2.2 Sensitivity and Uncertainty Study with a Focus on Aerosols, Based on Phébus Test Fpt1

Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1

Contact Info

Product

Resources

About