Development and Application of Cooling Characteristic Analysis Code for Molten Debris Bed

Fang Yu; Yang Shengxing; Gong Houjun; Zan Yuanfeng; Yang Zumao; Zhuo Wenbin

doi:10.13832/j.jnpe.2023.05.0047

Volume 44 Issue 5

Oct. 2023

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Fang Yu, Yang Shengxing, Gong Houjun, Zan Yuanfeng, Yang Zumao, Zhuo Wenbin. Development and Application of Cooling Characteristic Analysis Code for Molten Debris Bed[J]. Nuclear Power Engineering, 2023, 44(5): 47-53. doi: 10.13832/j.jnpe.2023.05.0047

Citation:

Fang Yu, Yang Shengxing, Gong Houjun, Zan Yuanfeng, Yang Zumao, Zhuo Wenbin. Development and Application of Cooling Characteristic Analysis Code for Molten Debris Bed[J]. Nuclear Power Engineering, 2023, 44(5): 47-53. doi: 10.13832/j.jnpe.2023.05.0047

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Development and Application of Cooling Characteristic Analysis Code for Molten Debris Bed

doi: 10.13832/j.jnpe.2023.05.0047

China National Nuclear Corporation Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institude of China, Chengdu, 610213, China

Received Date: 2022-11-14
Rev Recd Date: 2023-01-13
Publish Date: 2023-10-13

Abstract

Abstract

To analyze the cooling characteristics of debris bed formed in the late stage of severe accident in pressurized water reactor, an analysis code for molten debris bed cooling was developed. Based on the one-dimensional six-equation two-phase flow model, the physical process of two-phase flow and heat transfer in the debris bed was described by using the porous medium flow boiling heat transfer model, and the equations were discretized and solved by using the controlled volume integral method, semi-implicit method and first-order upwind scheme. The results of TUTU, COOLOCE and STYX experiments were used to validate the model from aspects: two-phase flow and dry-out heat flux (DHF). It was found that Hu&Theofanous model and Reed model had better prediction results for the two-phase flow of debris bed with relatively large particle size, while Lipinski model had higher prediction accuracy for the low-pressure DHF of small particle debris bed. The cooling capacity of molten debris bed in severe accident of PWR was predicted by the code. At a particle heat release rate of 1 MW/m³, the cooling height of debris bed was 0.56 m under top-flooding condition; and the height increased to 0.85 m by using bottom-flooding driven by natural circulation.
- Severe accident,
- Debris bed,
- Porous media,
- Boiling heat transfer,
- Dry-out heat flux (DHF)

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References(15)

References

[1]	ERGUN S. Fluid flow through packed columns[J]. Chemical Engineering Progress, 1952, 48(2): 89-94.
[2]	LIPINSKI R J. A one-dimensional particle bed dryout model[J]. Transactions of the American Nuclear Society, 1981, 38: 386-387.
[3]	REED A W. The effect of channeling on the dryout of heated particulate beds immersed in a liquid pool[D]. Cambridge, USA: Massachusetts Institute of Technology, 1982.
[4]	TUNG V X, DHIR V K. A hydrodynamic model for two-phase flow through porous media[J]. International Journal of Multiphase Flow, 1988, 14(1): 47-65. doi: 10.1016/0301-9322(88)90033-X
[5]	LI L X, ZOU X M, LOU J J, et al. Pressure drops of single/two-phase flows through porous beds with multi-sizes spheres and sands particles[J]. Annals of Nuclear Energy, 2015, 85: 290-295. doi: 10.1016/j.anucene.2015.05.025
[6]	SCHMIDT W. Interfacial drag of two-phase flow in porous media[J]. International Journal of Multiphase Flow, 2007, 33(6): 638-657. doi: 10.1016/j.ijmultiphaseflow.2006.09.006
[7]	LINDHOLM I, HOLMSTRÖM S, MIETTINEN J, et al. Dryout heat flux experiments with deep heterogeneous particle bed[J]. Nuclear Engineering and Design, 2006, 236(19-21): 2060-2074. doi: 10.1016/j.nucengdes.2006.03.036
[8]	RAHMAN S. Coolability of corium debris under severe accident conditions in light water reactors[D]. Stuttgart: Universität Stuttgart, 2013.
[9]	RAVERDY B, MEIGNEN R, PIAR L, et al. Capabilities of MC3D to investigate the coolability of corium debris beds[J]. Nuclear Engineering and Design, 2017, 319: 48-60. doi: 10.1016/j.nucengdes.2017.04.005
[10]	HU K, THEOFANOUS T G. On the measurement and mechanism of dryout in volumetrically heated coarse particle beds[J]. International Journal of Multiphase Flows, 1991, 17(4): 519-532. doi: 10.1016/0301-9322(91)90047-7
[11]	SCHULENBERG T, MULLER U. An improved model for two-phase flow through beds of coarse particles[J]. International Journal of Multiphase Flow, 1987, 13(1): 87-97. doi: 10.1016/0301-9322(87)90009-7
[12]	ROHSENOW W M. A method of correlating heat transfer data for surface boiling of liquids[J]. Heat Transfer, 1952, 74(4): 969-973.
[13]	LIENHARD J H. A heat transfer textbook[M]. Englewood Cliffs: Prentice-Hall, 1987: 457.
[14]	TUTU N K, GINSBERG T, CHEN J C. Interfacial drag for two-phase flow through high permeability porous beds[J]. Journal of Heat Transfer, 1984, 106(4): 865-870. doi: 10.1115/1.3246765
[15]	TAKASUO E, HOLMSTRÖM S, KINNUNEN T, et al. The COOLOCE experiments investigating the dryout power in debris beds of heap-like and cylindrical geometries[J]. Nuclear Engineering and Design, 2012, 250: 687-700. doi: 10.1016/j.nucengdes.2012.06.015