Share This Article:

RETRACTED: 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

Abstract Full-Text HTML Download Download as PDF (Size:3451KB) PP. 504-522
DOI: 10.4236/eng.2019.118035    205 Downloads   427 Views  
Author(s)    Leave a comment


Short Retraction Notice

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This article has been retracted to straighten the academic record.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.

The full retraction notice in PDF is preceding the original paper which is marked "RETRACTED".

Conflicts of Interest

The authors declare no conflicts of interest regarding the publication of this paper.

Cite this paper



[1] Theofanous, T.G., Liu, C., Angelini, S. and Salmassi, T. (1997) In-Vessel Coolability & Retention of a Core Melt. International Journal of Nuclear Engineering & Design, , 169, 1-48.
[2] Sehgal, B.R. (2012) Nuclear Safety in Light Water Reactors, Severe Accident Phenomenology. Academic Press, New York, 119.
[3] Nourgaliev, R.R., Dinh, T.N. and Sehgal, B.R. (1997) Effect of Fluid Prandtl Number on Heat Transfer Characteristics in Internally Heated Liquid Pools with Rayleigh Numbers up to 1012. Nuclear Engineering and Design, 169, 165-184.
[4] Kulacki, F.A. and Goldstein, R.J. (1972) Thermal Convection in a Horizontal Fluid Layer with Uniform Volumetric Energy Sources. Journal of Fluid Mechanics, 55, 271-287.
[5] Kulacki, F.A. and Nagle, M.E. (1975) Natural Convection in a Horizontal Fluid Layer with Volumetric Energy Sources. Journal of Heat Transfer, 97, 204-211.
[6] Kulacki, F.A. and Emara, A.A. (1975) High Reynolds Number Convection in Enclosed Fluid Layers with Internal Heat Sources. US NRC Report NUREG-75/065.
[7] Asmolov, V. and Tsurikov, D. (2014) MASCA Project: Major Activities and Results. RRC Kurchatov Institute, Moscow.
[8] Asmolov, V. (1997) Latest Findings of RASPLAV Project. NSI Russian Research Center Kurchatov Institute, Moscow.
[9] Sehgal, B.R., Bui, V.A., Dinh, T.N., Green, J.A. and Kolb, G. (1998) SIMECO Experiments on In-Vessel Melt Pool Formation and Heat Transfer with and without a Metallic Layer. Proceedings of In-Vessel Core Debris Retention and Coolability Workshop, Garching, 3-6 March 1998, 205-213.
[10] Gaus-Liu, X., Miassoedov, A., Cron, T. and Wenz, T. (2010) In-Vessel Melt Pool Coolability Test-Description and Results of LIVE Experiments. Nuclear Engineering & Design, 240, 3898-3903.
[11] Zhang, L., Zhang, Y.P., Zhao, B., Ma, W.M. and Zhou, Y.K. (2016) COPRA: A Large Scale Experiment on Natural Convection Heat Transfer in Corium Pools with Internal Heating. Progress in Nuclear Energy, 86, 132-116.
[12] ANSYS, Inc. (2016) ANSYS FLUENT Theory Guide. Release 16.2, Canonsburg.
[13] Tran, C.T. and Dinh, T.N. (2008) Application of the Phase-Change Effective Convectivity Model to Analysis of Core Melt Pool Formation and Heat Transfer in a BWR Lower Head. Proceedings of the Annual Meeting of the American Nuclear Society, Anaheim, June 2008, 617-618.
[14] Tran, C.T. (2009) The Effective Convectivity Model for Simulation and Analysis of Melt Pool Heat Transfer in a Light Water Reactor Pressure Vessel Lower Head. PhD Thesis, Royal Institute of Technology, Stockholm.
[15] Steinberner, U. and Reineke, H.H. (1978) Turbulent Buoyance Convection Heat Transfer with Internal Heat Sources. Proceedings of the Sixth Internal Heat Transfer Conference, Vol. 2, Toronto, 305-310.
[16] Asfia, F.J., Frantz, B. and Dhir, V.K. (1996) Experimental Investigation of Natural Convection in Volumetrically Heated Spherical Segments. Journal of Heat Transfer, 118, 31-37.
[17] Asfia, F.J. and Dhir, V.K. (1996) An Experimental Study of Natural Convection in a Volumetrically Heated Spherical Pool Bounded on Top with a Rigid Wall. Nuclear Engineering and Design, 163, 333-348.
[18] Asfia, F.J. (1995) Experimental Investigation of Natural Convection Heat Transfer in Volumetrically Heated Spherical Segments. PhD Thesis, University of California, Los Angeles.
[19] Dinh, T.N., Nigmatulin, B.I., Nourgaliev, R.R. and Rassokhin, N.G. (1996) Assessment of the Thermal Load When Molten Debris Interacts with a VVER Reactor Vessel during a Severe Accident. Teploenergetika (Moscow), No. 3, 9-17.
[20] Rassokhin, N.G., Mukhtarov, E.S., Granovskii, V.S., et al. (1996) On Simulating Physical Processes during the Interaction of the Core Melt with the Reactor Vessel. Vestnik MEI (Moscow), No. 3, 27-40.
[21] Greene, G.A., Hartnett, J.P., Irvine Jr., T.F. and Cho, Y.I. (2001) Heat Transfer in Nuclear Reactor Saf. Volume 29.
[22] Tran, C.T. and Dinh, T.N. (2009) The Effective Convectivity Model for Simulation of Melt Pool Heat Transfer in a Light Water Reactor Lower Head. Part II. Model Assessment and Application. Progress in Nuclear Energy, 51, 860-871.
[23] Komlev, A., Konovalenko, A., Ma, W., Villanueva, W., Yu, P., Laato, T., Karbojian, A., Sköld, P. and Bechta, S. (2015) IVMR Living Document, Internal Material. KTH, Stockholm.
[24] ANSYS, Inc. (2017) ANSYS FLUENT Theory Guide. Release 17.1, Canonsburg.
[25] Kim, S.-H., Prk, H.-K. and Chung, B.-J. (2016) Mass Transfer Experiments for the Heat Load during In-Vessel Retention of the Core Melt. Nuclear Engineering & Technology, 48, 906-914.

comments powered by Disqus

Copyright © 2020 by authors and Scientific Research Publishing Inc.

Creative Commons License

This work and the related PDF file are licensed under a Creative Commons Attribution 4.0 International License.