Demonstration of the heat removing capabilities of the EPR core catcher

Fischer, M.; Herbst, Oliver; Schmidt, Holger

doi:10.1016/j.nucengdes.2005.02.022

Cited by 24 publications

(8 citation statements)

References 2 publications

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“…The cold crucible technique has been adopted for the EPR TM [19] that features a spreading room adjacent to the reactor pit in which the melt is cooled by water from the bottom and top after spreading is completed. An extensive series of full scale experiments were performed in order characterize the heat removal capabilities of this cooling structure [20]. The VVER-1000 also utilizes a crucible technique, but in this design the crucible is located directly below the reactor vessel [21].…”

Section: Category 2 Studiesmentioning

confidence: 99%

OECD MCCI-2 Project. Final Report

Farmer

Lomperski

Kilsdonk

et al. 2010

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Section: Category 2 Studiesmentioning

confidence: 99%

OECD MCCI-2 Project. Final Report

Farmer

Lomperski

Kilsdonk

et al. 2010

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“…The researches for core catcher design have been focused mainly on the verification of its performance to reinforce the safety of advanced light water reactors (LWRs). AREVA carried out critical heat flux experiment for the core catcher of European PWR and verified that the measured maximum heat flux at the heating surface under the condition of low mass flow rate of 0.1∼0.2 kg/s did not exceed critical heat flux [4]. Toshiba performed a natural circulation test using a fanshaped test facility and confirmed a cooling performance of a round-shaped core catcher for an advanced boiling water reactor [5].…”

Section: Introductionmentioning

confidence: 72%

Assessment of the MARS Code Using the Two-Phase Natural Circulation Experiments at a Core Catcher Test Facility

Lee¹,

Choi²,

Ha³

et al. 2017

Science and Technology of Nuclear Installations

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A core catcher has been developed to maintain the integrity of nuclear reactor containment from molten corium during a severe accident. It uses a two-phase natural circulation for cooling molten corium. Flow in a typical core catcher is unique because (i) it has an inclined cooling channel with downwards-facing heating surface, of which flow processes are not fully exploited, (ii) it is usually exposed to a low-pressure condition, where phase change causes dramatic changes in the flow, and (iii) the effects of a multidimensional flow are very large in the upper part of the core catcher. These features make computational analysis more difficult. In this study, the MARS code is assessed using the two-phase natural circulation experiments that had been conducted at the CE-PECS facility to verify the cooling performance of a core catcher. The code is a system-scale thermal-hydraulic (TH) code and has a multidimensional TH component. The facility was modeled by using both one-and three-dimensional components. Six experiments at the facility were selected to investigate the parametric effects of heat flux, pressure, and form loss. The results show that MARS can predict the two-phase flow at the facility reasonably well. However, some limitations are obviously revealed.

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“…If reactor core debris penetrates the reactor pressure vessel, it will enter into the spreading area, which spreads the corium in a compartment provided with a protective layer and a special cooling system. The water in the in-containment refueling water storage tank will flow into the compartment and passively submerge the corium (Steinwarz et al, 2001;Wittmaack, 2002;Fischer et al, 2005). To keep the pressure within the containment below the design limit, the active containment heat removal system, which will be cooled by two separate dedicated trains of cooling water system and service water system, is used to cool the containment.…”

Section: Overall Performancementioning

confidence: 99%

Generation III pressurized water reactors and China’s nuclear power

Wang¹,

Ma²,

Fang³

2016

J. Zhejiang Univ. Sci. A

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Abstract:The design philosophy, overall performance, safety, and economy of three typical generation III (GIII) pressurized water reactors, EPR, AES2006, and CAP1400, are analyzed comprehensively in this paper. Based on comparison with and the lessons learned from the Fukushima nuclear accident, we forecast a future reactor for China's commercial nuclear power plant. Moreover, we put forward important technological fields of GIII nuclear power plants to which attention should be paid, including the enhancement of defense in depth, defense against extreme external events, severe accident mitigation, design simplification and standardization, improvement in economic competitiveness, load following capability, and adaptation to climate change.

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Demonstration of the heat removing capabilities of the EPR core catcher

Cited by 24 publications

References 2 publications

OECD MCCI-2 Project. Final Report

OECD MCCI-2 Project. Final Report

Assessment of the MARS Code Using the Two-Phase Natural Circulation Experiments at a Core Catcher Test Facility

Generation III pressurized water reactors and China’s nuclear power

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