0
Research Papers

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

[+] Author and Article Information
X. Gaus-Liu

Institute for Nuclear and Energy Technologies,
Karlsruhe Institute of Technology,
Hermann-von Helmholtz-Platz 1,
Eggenstein-Leopoldshafen 76344, Germany
e-mail: xiaoyang.gaus-liu@kit.edu

A. Miassoedov

Institute for Nuclear and Energy Technologies,
Karlsruhe Institute of Technology,
Hermann-von Helmholtz-Platz 1,
Eggenstein-Leopoldshafen 76344, Germany
e-mail: alexei.miassoedov@kit.edu

1Corresponding author.

Manuscript received September 22, 2016; final manuscript received January 25, 2017; published online May 25, 2017. Assoc. Editor: Guoqiang Wang.

ASME J of Nuclear Rad Sci 3(3), 031003 (May 25, 2017) (11 pages) Paper No: NERS-16-1107; doi: 10.1115/1.4035853 History: Received September 22, 2016; Revised January 25, 2017

This study investigates heat transfer characters of a volumetrically heated melt pool in LWR lower plenum. Experimental restrictions on prediction reliability are discussed. These restrictions include cooling boundary conditions, vessel geometries, and simulant melt selection on general and localized heat transfer. A survey of existing heat transfer correlations derived from individual experimental definitions is presented. The inconsistency in parameter definitions in Nu–Ra correlations is discussed. Furthermore, the discrepancy of upward Nu depending on the existence of crust is stressed. Several serials of experiments with different combinations boundary condition of external cooling and top cooling were performed in LIVE3D and LIVE2D facilities. The experiments were conducted with simulants with and without crust formation. The influences of cooling boundary conditions, the vessel geometry, and the simulant material on overall heat transfer as well as on heat flux distribution are analyzed. This paper provides own explanations about the discrepancies among the exiting heat transfer correlations and recommends the most suitable descriptions of melt pool heat transfer under different accident management strategies.

FIGURES IN THIS ARTICLE
<>
Copyright © 2017 by ASME
Your Session has timed out. Please sign back in to continue.

References

Theofanous, T. , Maguire, M. , Angelini, S. , and Salmassi, T. , 1997, “ The First Results From the ACOPO Experiment,” Nucl. Eng. Des., 169(1–3), pp. 49–57. [CrossRef]
Camila, V. , Gabriel, R. , and Jian, S. , 2010, “ Computational Simulation of Natural Convection of a Molten Core in Lower Head of a PWR Pressure Vessel,” 13th Brazilian Congress of Thermal Sciences of Engineering, Uberlandia, Brazil, Dec. 5–10.
Strizhov, V. , 2003, “ Molten Pool Heat Transfer,” EUROCOURSE 2003 Corium: Severe Accident R&D and Nuclear Power Plant Safety, Aix en Provence, France, Jan. 27–31.
Oertel, H. , and Delfs, J. , 1996, Strömungsmechanische Instabilitäten, U. Karlsruhe , ed., Springer Verlage, Berlin, pp. 44–45.
Asfia, F. , and Dhir, V. , 1996, “ An Experimental Study of Natural Convection in a Volumetrically Heated Spherical Pool Bounded on Top With a Rigid Wall,” Nucl. Eng. Des., 163(3), pp. 333–348. [CrossRef]
Dinh, T. , Nourgaliev, R. , and Sehgal, B. , 1997, “ On Heat Transfer Characteristics of Real and Simulant Melt Pool Experiments,” Nucl. Eng. Des., 169(1–3), pp. 151–164. [CrossRef]
Bernaz, L. , Bonnet, J. , Spindler, B. , and Villermaux, C. , 1998, “ Thermohydraulic Phenomea in Corium Pools: Numerical Simulation With TOLBIAC and Experimental Validation With BALI,” Workshop on In-Vessel Core Debris Retention and Coolability, Garching, Germany, Mar. 3–6.
Bonnet, J. , and Seiler, J. , 1999, “ Thermal Hydraulic Phenomena in Corim Pools: The BALI Experiment,” 7th International Conference on Nuclear Engineering (ICONE 7), Tokyo, Japan, Apr. 19–23.
Helle, M. , Kymäläinen, O. , and Tumosito, H. , 1998, “ Experimental Data on Heat Flux Distribution From a Volumetrically Heated Pool With Frozen Boundaries,” Workshop on In-Vessel Core Debris Retention and Coolability, Garching, Germany.
Kolb, G. , Theerthan, S. , and Sehgal, B. , 2000, “ Experiments on In-Vessel Melt Pool Formation and Convection With NaNO3-KNO3 Salt Mixture as Melt Simulant,” 8th International Conference on Nuclear Engineering (ICONE 8), Baltimore, MD, Apr. 2–6.
Jahn, M. , and Reinecke, M. , 1974, “ Free Convection Heat Transfer With Internal Heat Sources Calculations and Measurements,” 5th International Heat Transfer Conference, Tokyo, Japan, Sept. 1–6, Vol. 3, p. 74.
Mayinger, F. , Jahn, M. , Reineke, H. , and Steinberner, U. , 1975, “ Untersuchung thermohydraulischer Vorgänge sowie Wärmeaustausch in der Kernschmelze,” Bundesministerium für Forschung und Technologie, Bonn, Germany.
Steinberner, U. , and Reinecke, H. , 1978, “ Turbulent Bouyancy Convection Heat Transfer With Internal Heat Sources,” 6th International Heat Transfer Conference (IHTC-6), Toronto, ON, Canada, Aug. 7–11, pp. 305–310.
Kymäläinen, O. , Tuomisto, H. , Hongisto, O. , and Theofanous, T. , 1994, “ Heat Flux Distribution From a Volumetrically Heated Pool With High Rayleigh Number,” Nucl. Eng. Des., 149(1–3), pp. 401–408. [CrossRef]
Helle, M. , Kymäläinen, O. , and Tuomisto, H. , 1999, “ Experimental COPO II Dara on Nature Convection Homogenous and Stratified Pools,” 9th International Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-9), San Francisco, CA, Oct. 3–8.
Asmolov, V. , Abalin, S. , Surenkov, A. , Gnidoi, I. , and Strizhov, V. , 1998, “ Results of Salt Experiments Performed During Phase I of RASPLAV Project, RP-TR-33,” Russian Research Centre, Kurchatov Institute, Moscow, Russia.
Gaus-Liu, X. , and Miassoedov, A. , 2013, “ LIVE Experimental Results of Melt Pool Behaviour in the PWR Lower Head With Insulated Upper Lid and External Cooling,” ASME Paper No. ICONE21-15204.
Zhang, Y. , Zhang, L. , Zhou, Y. , Tian, W. , Qiu, S. , Su, G. , Zhao, B. , Yuan, Y. , and Ma, R. , 2016, “ Natural Convection Heat Transfer Test for In-Vessel Retention at Prototypic Rayleigh Numbers-Results of COPRA Experiments,” Prog. Nucl. Energy, 86, pp. 80–86. [CrossRef]
Gaus-Liu, X. , Miassoedov, A. , Fluhrer, B. , and Cron, T. , 2014, “ Experimental Results of In-Vessel Melt Pool Behaviour With Surface Insulation and Surface Cooling Conditions From LIVE3D and LIVE 2D Facilities,” 19th Pacific Basin Nuclear Conference, Vancouver, BC, Canada, Aug. 24–28.
Gaus-Liu, X. , Miassoedov, A. , Cron, T. , Foit, J. , Wenz, T. , and Schmidt-Stiefel, S. , 2010, “ Core Melt Solidification Characteristics in RPV Lower Head. Experimental Results From Live-Tests,” ASME J. Eng. Gas Turbines Power, 132(10), p. 102924. [CrossRef]
Pham, Q. T. , Seiler, J. M. , Combeau, H. , Gaus-Liu, X. , Kretzschmar, F. , and Miassoedov, A. , 2013, “ Modeling of Heat Transfer and Solidification in LIVE L3A Experiment,” Int. J. Heat Mass Transfer, 58(1–2), pp. 691–701. [CrossRef]

Figures

Grahic Jump Location
Fig. 1

Turbulent regimes in a melt pool with top and side wall cooling

Grahic Jump Location
Fig. 6

LIVE 3D normalized temperature distribution

Grahic Jump Location
Fig. 7

LIVE 2D normalized temperature distribution

Grahic Jump Location
Fig. 8

Melt temperature fit curves of LIVE3D and LIVE2D tests

Grahic Jump Location
Fig. 9

Normalized heat flux distribution through vessel wall in LIVE 3D tests

Grahic Jump Location
Fig. 4

LIVE-Nuup in comparison with former predictions and experimental results

Grahic Jump Location
Fig. 5

LIVE-Nudn in comparison with former predictions and experimental results

Grahic Jump Location
Fig. 10

Normalized heat flux distribution through vessel wall in LIVE 2D tests

Grahic Jump Location
Fig. 11

Heat flux fit curves of LIVE3D and LIVE2D tests

Grahic Jump Location
Fig. 12

Normalized heat flux distribution of LIVE 3D tests in comparison with other predictions

Grahic Jump Location
Fig. 2

LIVE3D test facility. Top: with top insulation lid, bottom: with cooling lid.

Grahic Jump Location
Fig. 3

Infrared image of the turbulent pattern on melt free surface

Grahic Jump Location
Fig. 13

Heat balance between heat power input and the total heat rate through external cooling and top cooling lid in LIVE-L7V test

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In