Overview of the facility and experiments performed in Phébus FP

March, P.; Simondi-Teisseire, B.

doi:10.1016/j.anucene.2013.03.040

Cited by 37 publications

(11 citation statements)

References 2 publications

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“…Five integral tests were performed, investigating the main processes affecting the severe degradation of the nuclear fuel and control rods, the release of FPs and control materials, their transport through the reactor coolant circuit, and their deposition as aerosols in the containment vessel [4][5][6]. Different fuel burn-up levels, control rod materials, and thermal-hydraulic conditions were investigated [7]. The Phébus research program has provided a comprehensive database to improve the understanding of the various phenomena leading to fission product behavior.…”

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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“…Phébus FPT experiments of Institut de Radioprotection et de Sûreté Nucléaire (IRSN) started in 1988 to study strategies for reactor core meltdown accidents and determine the radioactive releases to the environment [25]. The latter includes the study on fission product behavior in Phébus FPT containment vessel, which is the main focus of this research.…”

Section: Phébus Fpt3 Experimentsmentioning

confidence: 99%

“…Phébus FPT3 experiment studied the effects of degradation of boron carbide (B 4 C) control rod and fuel, and the behaviors of gaseous iodine and cesium aerosols in the containment vessel [6]. Phébus FPT3 experiment [25] starts the transient from degradation phase which lasts about 5-6 hours. There is oxidation of fuels and control rods under steam-poor environment.…”

Section: Phébus Fpt3 Experimentsmentioning

confidence: 99%

“…Design conditions are shown in Table 9. Temperature and pressure in the containment vessel are set at 383 K and 2.1 bar because the steam is fed in the degradation phase [25]. Wall temperature is set using heat slap at 383 K. Steam is flown into the containment vessel at the rate shown in Figure 6.…”

Section: Modification Of Aerosol Deposition Models In Art Modmentioning

confidence: 99%

“…Iodine (I) and cesium (Cs) are dominant fission products in containment vessel [6]. Various cesium compounds including cesium iodine (CsI), cesium hydroxide (CsOH), and cesium molybdate (Cs 2 MoO 4 ) are assumed to be released from the reactor core and have been actively investigated [6,7,24,25]. CsI can be obtained when the released Cs reacts promptly with I. CsOH occurs when the amount of released cesium excesses that of iodine [24].…”

Section: Introductionmentioning

confidence: 99%

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Validation of Modified ART Mod 2 Code through Comparison with Aerosol Deposition of Cesium Compound in Phébus FPT3 Containment Vessel

Vechgama¹,

Silva²,

Rassame

2019

Science and Technology of Nuclear Installations

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Evaluation of aerosol deposition in the containment vessel is an important step for the assessment of radioactive material release to the environment. ART Mod 2 is a calculation code that is used for evaluation of aerosol deposition in the containment vessel. The authors modified aerosol deposition models of ART Mod 2, namely, gravitational settling model, Brownian diffusion model, diffusiophoresis model, and thermophoresis model in order to increase potential of capturing the deposition phenomena. This study aims to compare the simulated results of modified ART Mod 2 with aerosol deposition of cesium compounds in the containment vessel of Phébus FPT3 experiment, in order to validate modified ART Mod 2 code. It is found that aerosol deposition using modified ART Mod 2 agrees with Phébus FPT3. Prediction of Brownian diffusion is significantly improved due to the consideration of turbulent damping process. Cesium mass flow rate and aerosol size are factors that can significantly influence the uncertainty of the results. When conditions of single volumes are carefully selected to match those of the Phébus FPT3 experiment, modified ART Mod 2 can predict aerosol deposition in Phébus FPT3 with relative accuracy.

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