Corium Behavior in the Lower Plenum of the Reactor Vessel Under Ivr-Ervc Condition: Technical Issues

Park, Raejoon; Kang, Kyoung-Ho; Hong, Sup; Kim, Sang-Baik; Song, J. H.

doi:10.5516/net.03.2012.701

Cited by 26 publications

(10 citation statements)

References 25 publications

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“…It must be indicted that MASCA (Rempe et al, 2008;Bechta et al, 2008;Tsurikov et al, 2007) and RASPLAV (Park et al, 2012) raised a three-layered structure (bottom-to-top): molten "heavy" metal-molten oxides-molten "light" metal. There are still in serious doubts for the great difference between the experiment and real molten core in three-layered structure, such as the heating method and the process of test.…”

Section: Referencesmentioning

confidence: 98%

Turbulent convection experiment at high Rayleigh number to support CAP1400 IVR strategy

et al. 2015

Nuclear Engineering and Design

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Section: Referencesmentioning

confidence: 98%

Turbulent convection experiment at high Rayleigh number to support CAP1400 IVR strategy

et al. 2015

Nuclear Engineering and Design

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“…1B. If there is sufficient zirconium in the molten corium, uranium metal is able to be extracted from the oxidic pool to the metal layer [1]. Thereafter, dense materials in the metal layer successively go down to the bottom of the RPV, which make the heavy metal layer.…”

Section: Molten Corium Behaviorsmentioning

confidence: 99%

“…In this study, two kinds of multi-layered configurations were assumed based on a recent piece of research [1]. Fig.…”

Section: Molten Corium Behaviorsmentioning

confidence: 99%

“…The concept of ERVC can be attained by supplying cooling water into the reactor cavity to take the heat from the external surface of the RPV. Hence, the overall understanding of complex phenomena during a severe accident is crucial, including the reactor vessel failure under ERVC conditions as well as corium behaviors in the lower plenum and thermal loads from the corium [1]. Although both thermalehydraulic and structural assessment are necessary in order to establish effective ERVC strategies, lots of previous studies have focused on determining critical heat flux (CHF) of the RPV outer wall because it has been known as a promising criterion.…”

Section: Introductionmentioning

confidence: 99%

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Structural assessment of reactor pressure vessel under multi-layered corium formation conditions

Kim

Chang

2015

Nuclear Engineering and Technology

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a b s t r a c tExternal reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one of the most useful strategies to mitigate severe accidents. However, reliability of this common idea is weakened because many studies were focused on critical heat flux whereas there were diverse uncertainties in structural behaviors as well as thermalehydraulic phenomena. In the present study, several key factors related to molten corium behaviors and thermal characteristics were examined under multi-layered corium formation conditions. Thereafter, systematic finite element analyses and subsequent damage evaluation with varying parameters were performed on a representative reactor pressure vessel (RPV) to figure out the possibility of high temperature induced failures. From the sensitivity analyses, it was proven that the reactor cavity should be flooded up to the top of the metal layer at least for successful accomplishment of the IVR-ERVC strategy. The thermal flux due to corium formation and the relocation time were also identified as crucial parameters. Moreover, three-layered corium formation conditions led to higher maximum von Mises stress values and consequently shorter creep rupture times as well as higher damage factors of the RPV than those obtained from two-layered conditions.

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“…Consequently, thinning of the vessel wall and other structural materials may lead to failure of the vessel. Ablation of the vessel wall is also a key phenomenon, which determines validity of IVR (in-vessel retention) of corium [2]. Hence, accurate modeling and prediction of ablation is essential for understanding severe accident progression as well as for development of IVR concepts.…”

mentioning

confidence: 99%

Analysis of Pb-Bi Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method

Masumura¹,

Yamaji²,

Furuya³

2015

JEPE

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Abstract:In a severe accident of a light water reactor, ablation of the RPV (reactor pressure vessel) lower head by corium is a key phenomenon, which affects progression of the accident. The MPS (moving particle semi-implicit) method is one of particle methods that calculate behavior of incompressible fluid by semi-implicit method. In preceding studies, the MPS method has been extensively studied and developed for simulations of different phenomena involved in severe accident of nuclear reactors. This paper aims to investigate whether the MPS method is capable of analyzing the lower head ablation phenomenon. The small-scale experiment carried out at CRIEPI (Central Research Institute of Electric Power Industry) using Pb-Bi vessel and silicone oil was analyzed for the validation of the MPS method. The MPS analysis well reproduced the experimental phenomena qualitatively. However, with respect to some quantitative results, more investigation such as influence of the calculation particle size is necessary.

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Corium Behavior in the Lower Plenum of the Reactor Vessel Under Ivr-Ervc Condition: Technical Issues

Cited by 26 publications

References 25 publications

Turbulent convection experiment at high Rayleigh number to support CAP1400 IVR strategy

Turbulent convection experiment at high Rayleigh number to support CAP1400 IVR strategy

Structural assessment of reactor pressure vessel under multi-layered corium formation conditions

Analysis of Pb-Bi Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method

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