Heat Transfer Mechanism by Natural Circulation for Cooling
Material in Nuclear Reactors as a Passive Safety System
Novitrian
1
, Khairul Basar
1
and Robi Dany Riupassa
2
1
Nuclear Physics & Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences,
Institut Teknologi Bandung, Indonesia
2
Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Indonesia
Keywords: natural circulation, computational fluid dynamics
Abstract: Natural circulation in nuclear reactor cooling systems can be modeled based on computational fluid
dynamics (CFD). Modeling is done to study the fluid flow in a closed loop system that occurs due to
differences in fluid density. The closed loop system model is fitted with a heater and cooler on the opposite
side. Because the density of the fluid depends on the temperature, then by adjusting the temperature
difference between the heater and the cooler it can produce a fluid flow that occurs naturally. The initial
condition in this study uses water as a working fluid with flow properties that are laminar and
incompressible. Variations in temperature differences between heaters and coolers are done to get the
temperature distribution and fluid flow velocity. The model is built for time-dependent conditions so that
the time needed to transfer heat in a closed loop system can be known. Variations in temperature differences
between heaters and coolers are carried out until the maximum conditions of water temperature to remain in
the liquid phase. For this condition the maximum temperature is set to 80 C. This research was also
developed by using several other types of fluids to determine the effect of density on fluid flow velocity.
Other fluids used are gasoline, liquid helium, liquid sodium, and liquid mercury. The height of the closed
loop system at the beginning of this study was used by three meters which then varied for heights of up to
five and eight meters. Model testing is also carried out for working temperatures with differences between
heaters and coolers above 80 C.
1 INTRODUCTION
The nuclear reactor accident that occurred at
Fukushima-Daiichi in 2011 made public acceptance
of nuclear reactor technology decrease. Nuclear
reactors that are in operation now and that are being
developed are expected to have a high level of
safety. Some conditions that can cause reactor
accidents such as pump failure or reactor power loss
must be overcome as well as possible.
The phenomenon of natural circulation is used as
a mechanism of passive cooling in nuclear reactors.
This mechanism will help to dispose of residual heat
in nuclear reactors when emergency conditions for
example due to pump failure. Testing natural
circulation systems can be done with experiments or
closed-loop system simulations. Previous studies
have conducted experiments with closed loop
systems with variations in temperature differences
between heaters and coolers.
In this study, the natural circulation in a nuclear
reactor cooling system is modeled using
computational fluid dynamics (CFD). Modeling is
done to study the fluid flow in a closed loop system
that occurs due to differences in fluid density
(Antariksawan, 2019). Calculations are made for
several conditions. First is the variation in
temperature differences between heating and
cooling, then the use of several types of fluid to see
the effect of fluid density on temperature
distribution, and also the height variation of closed-
loop system.
2 METHODOLOGY
The two-dimensional model for the closed loop
system in this study is shown in Figure 1.