COPRA: A large scale experiment on natural convection heat transfer in corium pools with internal heating

Zhang, Luteng; Zhang, Yapei; Zhao, Bo; Ma, Weimin; Zhou, Yukun; Su, G.H.; Tian, Wenxi; Qiu, Suizheng

doi:10.1016/j.pnucene.2015.10.006

Cited by 40 publications

(7 citation statements)

References 14 publications

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“…Water was used as the initial simulant in the first set of experiments (Zhang et al, 2016b). The data collected included melt pool temperature distribution, heat flux distribution along the vessel wall, and heat transfer towards the curved wall.…”

Section: Copra Experimentsmentioning

confidence: 99%

“…where, 𝑞 local is the local heat flux, 𝜆 wall is the thermal conductivity at the wall, 𝑇 is the temperature of the vessel wall, 𝛿 is the thickness of the vessel, 𝑅 is the vessel radius, and the subscripts 𝑖𝑛 and 𝑜𝑢𝑡 represent the inner and outer surface of the curved wall respectively. In this study, the average heat flux of the melt pool is calculated using the surface area-weighted average, identical to the method followed in the experiment (Zhang et al, 2016b). The weighted average of heat flux over the entire curved wall is derived as:…”

Section: Crust Distribution and Heat Fluxmentioning

confidence: 99%

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Numerical Study of the Effect of Geometry on the Behaviour of Internally Heated Melt Pools for In-Vessel Melt Retention

Venkateshwaran

Kumar

et al. 2022

SSRN Journal

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Section: Copra Experimentsmentioning

confidence: 99%

Section: Crust Distribution and Heat Fluxmentioning

confidence: 99%

Numerical Study of the Effect of Geometry on the Behaviour of Internally Heated Melt Pools for In-Vessel Melt Retention

Venkateshwaran

Kumar

et al. 2022

SSRN Journal

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“…These experiments include different geometrical facilities at a wide range of Rayleigh numbers and were studied extensively to understand the natural convection heat transfer phenomenon with an internally heated melt pool with high Rayleigh numbers. Zhang et al 33 demonstrated that the differences in the downward heat transfer from different experiments that appear in the high Rayleigh region would grow even larger with increasing Rayleigh numbers.…”

Section: Introductionmentioning

confidence: 99%

Experimental investigations on melt coolability with simulated decay heat—The influence of delay time in flooding

2021

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The primary objective of core catchers is to minimize the potential risk of core meltdown by stabilization and cooling of molten corium within the reactor containment for a prolonged period by strategically cooling it. Quenching of the high-temperature melt by top flooding strongly depends on the timing of injection of the cooling water, that is, immediate flooding or delayed flooding. To understand this aspect, we conducted experiments in a simulated core catcher of an Indian advanced nuclear reactor. In the experiments, sodium borosilicate glass, as a mixture of corium and sacrificial material simulant, was melted at about 1200°C and cooled by water from the side of a simulated core catcher and then flooding at the top of the melt pool. Two experiments were conducted; the first one was done with immediate flooding at the top of the melt pool; the second was performed with delayed top flooding of 45 min gap. The results show that immediate flooding quenches the melt pool rapidly compared to delayed flooding. A stable crust formation at the top of the melt pool and wall adhesion is observed in the delayed flooding. It was also found that no ingression of the water in the molten pool occurred with delayed flooding. On the other hand, with immediate flooding, water was found to ingress into the melt pool due to gap formations between melt and core catcher sidewall, causing the melt to break up through eruption by ingressed water. This phenomenon resulted in the formation of sand-type debris and in faster melt cooling.

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“…The main focus of the LIVE experimental program was to address remaining uncertainties in melt pool heat transfer with phase change. The COPRA (Corium Pool Research Apparatus) [11] experimental facility was designed to investigate the in-vessel molten corium pool behavior applying in different melt volumes, heat generation rates. It presented the behavior of a large-scale homogenous melt pool in transient and steady state conditions.…”

Section: Introductionmentioning

confidence: 99%

Numerical Assessment of Prandtl Number Effect on Transient Heat Flux Distribution Imposed on Nuclear Reactor Pressure Vessel by Application of PECM in a Volumetrically Heated Molten Pool

Khan¹

2019

ENG

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Retraction type (multiple responses allowed):  Unreliable findings   Lab error  Inconsistent data  Analytical error  Biased interpretation   Other:  Irreproducible results  Failure to disclose a major competing interest likely to influence interpretations or recommendations  Unethical research   Fraud   Data fabrication  Fake publication  Other:  Plagiarism  Self plagiarism  Overlap  Redundant publication *  Copyright infringement  Other legal concern:  Editorial reasons   Handling error  Unreliable review(s)  Decision error  Other: X Other: there are some errors in the discussion and conclusion part. Results of publication (only one response allowed): Xare still valid.  were found to be overall invalid. Author's conduct (only one response allowed):  honest error  academic misconduct Xnone (not applicable in this casee.g. in case of editorial reasons) * Also called duplicate or repetitive publication. Definition: "Publishing or attempting to publish substantially the same work more than once." History Expression of Concern:  yes, date: yyyy-mm-dd Xno Correction:  yes, date: yyyy-mm-dd Xno Comment: There are some errors in the discussion and conclusion part. This article has been retracted to straighten the academic record. In making this decision the Editorial Board follows COPE's Retraction Guidelines. Aim is to promote the circulation of scientific research by offering an ideal research publication platform with due consideration of internationally accepted standards on publication ethics. The Editorial Board would like to extend its sincere apologies for any inconvenience this retraction may have caused.

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COPRA: A large scale experiment on natural convection heat transfer in corium pools with internal heating

Cited by 40 publications

References 14 publications

Numerical Study of the Effect of Geometry on the Behaviour of Internally Heated Melt Pools for In-Vessel Melt Retention

Numerical Study of the Effect of Geometry on the Behaviour of Internally Heated Melt Pools for In-Vessel Melt Retention

Experimental investigations on melt coolability with simulated decay heat—The influence of delay time in flooding

Numerical Assessment of Prandtl Number Effect on Transient Heat Flux Distribution Imposed on Nuclear Reactor Pressure Vessel by Application of PECM in a Volumetrically Heated Molten Pool

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