Nuclear Engineering and Design 265 (2013) 210–221
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Nuclear Engineering and Design
j ourna l h om epa ge: www.elsevier.com/locate/nucengdes
Experiments and MPS analysis of stratification behavior of two
immiscible fluids
Gen Li
a,∗
, Yoshiaki Oka
a
, Masahiro Furuya
b
, Masahiro Kondo
b
a
Cooperative Major in Nuclear Energy, Waseda University, 3-4-1, Okubo, Shinjuku-ku, Tokyo 169-8555, Japan
b
Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry (CRIEPI), 2-11-1 Iwado-kita, Komae, Tokyo 201-8511, Japan
h i g h l i g h t s
•
Improving numerical stability of MPS method.
•
Implicitly calculating viscous term in momentum equation for highly viscous fluids.
•
Validation of the enhanced MPS method by analyzing dam break problem.
•
Various stratification behavior analysis by experiments and simulations.
•
Sensitivity analysis of the effects of the fluid viscosity and density difference.
a r t i c l e i n f o
Article history:
Received 1 May 2013
Accepted 2 September 2013
a b s t r a c t
Stratification behavior is of great significance in the late in-vessel stage of core melt severe accident of
a nuclear reactor. Conventional numerical methods have difficulties in analyzing stratification process
accompanying with free surface without depending on empirical correlations. The Moving Particle Semi-
implicit (MPS) method, which calculates free surface and multiphase flow without empirical equations,
is applicable for analyzing the stratification behavior of fluids. In the present study, the original MPS
method was improved to simulate the stratification behavior of two immiscible fluids. The improved MPS
method was validated through simulating classical dam break problem. Then, the stratification processes
of two fluid columns and injected fluid were investigated through experiments and simulations, using
silicone oil and salt water as the simulant materials. The effects of fluid viscosity and density difference
on stratification behavior were also sensitively investigated by simulations. Typical fluid configurations
at various parametric and geometrical conditions were observed and well predicted by improved MPS
method.
© 2013 Elsevier B.V. All rights reserved.
1. Introduction
Stratification behavior of fluids is an important phenomenon in
nature and traditional industry. It is also of great significance in
the late in-vessel stage of core melt severe accident of a nuclear
reactor. After water is boiled off from the Reactor Pressure Vessel
(RPV), a molten corium pool may form in the RPV lower head due
to the decay heat released from fission products. In that case, a
substantial amount of molten corium is collected into the lower
head, as happened in the TMI-2 accident. Following the principle
of phase equilibrium, the molten corium may separate into non-
miscible layers. Most available studies on the in-vessel retention
of molten corium usually consider the two-layer pool as the final
configuration, that is, the oxide layer under the light metal layer.
∗
Corresponding author. Tel.: +81 3 5286 8225; fax: +81 3 5286 8225.
E-mail addresses: ligen@fuji.waseda.jp, leageon@gmail.com (G. Li).
The thermo-hydraulics of the molten pool greatly influence
the distribution of thermal load across the vessel wall, and it has
been widely studied through experiments using simulant materi-
als, such as COPO (Kymäläinen et al., 1994), ACOPO (Theofanous
et al., 1997; Theofanous and Angelini, 2000), SIMECO (Sehgal et al.,
1998), RASPLAV-SALT (Asmolov et al., 2003) and BALI (Bonnet and
Seiler, 1999). The main objective of these studies is to investigate
the heat flux distribution surrounding a volumetrically heated melt
pool at a wide range of Rayleigh number. In addition, the chemi-
cal behavior of oxide corium in contact with structural materials
has been experimentally investigated by MASCA (Tsurikov et al.,
2007) using the prototypic core materials. It focuses on the effects
of iron content and oxidized degree of molten corium on the con-
figurations of the pool. Post-test results indicate that the molten
pool, initially a uniform mixture of components, separates into two
layers with different densities.
MAAP (Suh and Henry, 1996a,b), MELCOR (Gauntt et al., 2005)
and PECM (Tran and Dinh, 2009a,b) codes analyzed heat transfer
0029-5493/$ – see front matter © 2013 Elsevier B.V. All rights reserved.
http://dx.doi.org/10.1016/j.nucengdes.2013.09.006