New set of convective heat transfer coefficients established for pools and validated against CLARA experiments for application to corium pools

Michel, Bieth

doi:10.1016/j.nucengdes.2015.02.013

Cited by 3 publications

(1 citation statement)

References 20 publications

(20 reference statements)

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“…One have to note that recently, on the base of CLARA results, IRSN also established a new set of heat transfer correlations (Ref. [14]) taking into account a possible difference between the horizontal and the lateral superficial velocities resulting from a possible anisotropic ablation.…”

Section: Stmentioning

confidence: 99%

Molten Corium–Concrete Interaction: Investigation of convective heat transfer in a pool with gas sparging

Bottin

Amižić

Guyez

et al. 2016

Annals of Nuclear Energy

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During a severe accident in a Pressurized Water Reactor, corium may fall in the reactor pit and interact with concrete. The CLARA setup, financed by EDF, IRSN, GDF-Suez and CEA, has been designed to understand the heat transfer phenomena involved in the Molten Concrete Corium Interaction (MCCI). The facility is composed of a pool of simulant liquids, percolated by air and internally heated by direct electrical current. It is in contact with several heat exchangers in order to maintain walls at a constant temperature and to measure local heat losses. The experiments performed aimed at studying the influence of liquid viscosity (varying from 1 to 10000 mPa.s by dissolution of hydroxyethyl cellulose in the water), air injection velocities (ranging from 0 to 10 cm/s) on both horizontal and vertical walls and pool length, on heat transfer distribution. This paper presents the findings on heat transfer which would contribute to the understanding of MCCI. After a literature review on the existing heat transfer experiments and correlations for two-phase (liquid-gas) flow, the CLARA experiments are described. Then, the results obtained are presented: influence of superficial gas velocity and liquid properties (especially viscosity) on heat transfer, evaluation of ratio between heat transfer on vertical and horizontal interface, influence of the pool dimensions. Finally, the analysis and interpretation of CLARA experiments are given: comparison to the literature data, development of correlations concerning the heat transfer along the vertical and horizontal plate, comparison to results obtained with real materials.

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Section: Stmentioning

confidence: 99%

Molten Corium–Concrete Interaction: Investigation of convective heat transfer in a pool with gas sparging

Bottin

Amižić

Guyez

et al. 2016

Annals of Nuclear Energy

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Molten Core Concrete Interaction

Journeau¹,

Piluso²

2020

Comprehensive Nuclear Materials

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Convective Heat Transfer in PWR, BWR, CANDU, SMR, and MSR Nuclear Reactors—A Review

Sikorska,

Brzozowska,

Pawełkiewicz

et al. 2024

Energies

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Nuclear reactors are very complex units in which many physical processes occur simultaneously. Efficient heat removal from the reactor core is the most important of these processes. Heat is removed from the reactor core via heat conduction, radiation, and convection. Thus, convective heat transfer and its conditions play a crucial role in the operation and safety of nuclear reactors. Convective heat transfer in nuclear reactors is a very complex process, which is dependent on many conditions and is usually described by different correlations which combine together the most important criteria numbers, such as the Nusselt, Reynolds, and Prandtl numbers. The applicability of different correlations is limited by the conditions of heat transfer in nuclear reactors. The selection of the proper correlation is very important from the reactor design accuracy and safety points of view. The objective of this novel review is to conduct a comprehensive analysis of the models and correlations which may be applied for convective heat transfer description and modeling in various types of nuclear reactors. The authors review the most important research papers related to convective heat transfer correlations which were obtained by experimental or numerical research and applied calculations and heat transfer modeling in nuclear reactors. Special focus is placed on pressurized water reactors (PWRs), boiling water reactors (BWRs), CANDU reactors, small modular reactors (SMRs), and molten salt reactors (MSRs). For each type of studied reactor, the correlations are grouped and presented in tables with their application ranges and limitations. The review results give insights into the main research directions related to convective heat transfer in nuclear reactors and set a compendium of the correlations that can be applied by engineers and scientists focused on heat transfer in nuclear reactors. Prospective research directions are also identified and suggested to address the ongoing challenges in the heat transfer modeling of present and next-generation nuclear reactors.

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New set of convective heat transfer coefficients established for pools and validated against CLARA experiments for application to corium pools

Cited by 3 publications

References 20 publications

Molten Corium–Concrete Interaction: Investigation of convective heat transfer in a pool with gas sparging

Molten Corium–Concrete Interaction: Investigation of convective heat transfer in a pool with gas sparging

Molten Core Concrete Interaction

Convective Heat Transfer in PWR, BWR, CANDU, SMR, and MSR Nuclear Reactors—A Review

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