A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments

Haste, T.; Steinbrück, M.; Barrachin, M.; Luze, O. de; Große, M.; Stuckert, J.

doi:10.1016/j.nucengdes.2014.06.035

Cited by 29 publications

(11 citation statements)

References 34 publications

(46 reference statements)

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“…However, to alleviate this situation before too late, it is very important to learn about the core degradation early stage knowledge and make the probabilistic forecasting of severe accident sequence. The CORA experiments are very useful in helping us understand severe accident early stage phenomena and it also promotes the development of other severe accident early stage research (Haste et al, 2015).…”

Section: Experimental Research On Core Degradation and Melting Materimentioning

confidence: 99%

“…The PHEBUS experiment aims to solve International Standard Problem 46 which are the core degradation and melting materials migration problems (Gonnier et al, 1992;Schwarz et al, 1999;Clément and Zeyen, 2013;Haste et al, 2015). The research target of PHEBUS is to study the key in-vessel physical phenomenon, including core degradation, fossil fuel transportation, transformation, and relevant physical chemical phenomenon.…”

Section: Experimental Research On Core Degradation and Melting Materimentioning

confidence: 99%

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Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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Section: Experimental Research On Core Degradation and Melting Materimentioning

confidence: 99%

Section: Experimental Research On Core Degradation and Melting Materimentioning

confidence: 99%

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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“…Transient corium relocation from the core to the lower head has to be taken into account especially for LWR with heavy reflector (reflector thickness to ablate, stabilization with flooded down-comer, in-core corium pool stratification). Core degradation [10][11][12] is a combination of complex physical phenomena (thermal-hydraulics, oxidation of core materials, loss of core geometry) which could result in the corium pool formation in core and after to its propagation and its relocation in lower head.…”

Section: Introductionmentioning

confidence: 99%

“…So we assume that the core degradation [10][11][12] until the corium pool formation and the corium pool propagation could be modeled separately.…”

Section: Introductionmentioning

confidence: 99%

A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

Saas

Tellier

Bajard

2017

EPJ Nuclear Sci. Technol.

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Abstract. In the context of the simulation of the Severe Accidents (SA) in Light Water Reactors (LWR), we are interested on the in-core corium pool propagation transient in order to evaluate the corium relocation in the vessel lower head. The goal is to characterize the corium and debris flows from the core to accurately evaluate the corium pool propagation transient in the lower head and so the associated risk of vessel failure. In the case of LWR with heavy reflector, to evaluate the corium relocation into the lower head, we have to study the risk associated with focusing effect and the possibility to stabilize laterally the corium in core with a flooded down-comer. It is necessary to characterize the core degradation and the stratification of the corium pool that is formed in core. We assume that the core degradation until the corium pool formation and the corium pool propagation could be modeled separately. In this document, we present a simplified geometrical model (0D model) for the in-core corium propagation transient. A degraded core with a formed corium pool is used as an initial state. This state can be obtained from a simulation computed with an integral code. This model does not use a grid for the core as integral codes do. Geometrical shapes and 0D models are associated with the corium pool and the other components of the degraded core (debris, heavy reflector, core plate . . . ). During the transient, these shapes evolve taking into account the thermal and stratification behavior of the corium pool and the melting of the core surrounding components. Some results corresponding to the corium pool propagation in core transients obtained with this model on a LWR with a heavy reflector are given and compared to grid approach of the integral codes MAAP4.

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“…To date, a total of 17 QUENCH tests have been performed with different fuel/cladding materials and different boundary conditions for each test. Two tests were performed with B 4 C control rods, one with Ag-In-Cd control rods, and all other tests used a fuel rod simulator [1]. * Corresponding author.…”

Section: Introductionmentioning

confidence: 99%

Assessment of the models in RELAP/SCDAPSIM with QUENCH-06 analysis

Madokoro

Erkan

Okamoto

2015

Journal of Nuclear Science and Technology

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A fundamental principle of accident management in a nuclear power plant is the injection of water to cool the core. In this framework, a series of QUENCH tests have been conducted at Karlsruhe Institute of Technology (formerly Forschungszentrum Karlsruhe). The test results constitute a significant experimental database not only for further understanding of reflooding behavior, but also for code validation and improvement. The RELAP/SCDAPSIM code is a system code that is used to model reactor behavior and is widely used around the world. To date, assessment and validation have been performed with numerous experiments, including QUENCH tests. In the previous studies, the results of QUENCH simulations were referred to be sensitive to two main parameters: the electrical resistance and the thermal conductivity of the shroud insulator, which are subject to relatively large uncertainty. It is important to investigate these two parameters in detail, because this would enable identification of those SCDAP models that require further improvement. In this study, the uncertainty of the electrical resistance was reduced by modification of the code and subsequent validation with experimental data. In addition, modification of the thermal properties of the shroud insulator is suggested with consideration of the argon atmosphere in the facility. Finally, upcoming problems and questions are discussed. A rather good agreement was obtained than those of previous studies. As a result, more accurate modeling of the electrical resistance and the thermal properties of the shroud insulator was conducted and the importance of these parameters was evaluated.

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A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments

Cited by 29 publications

References 34 publications

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Review on Core Degradation and Material Migration Research in Light-Water Reactors

A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

Assessment of the models in RELAP/SCDAPSIM with QUENCH-06 analysis

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