Nuclear Science and Technology - Volume 10, Number 3, September 2020

Abstract: This study investigates short-range atmospheric transport of radiocesium (137Cs) after

Fukushima nuclear accident using the Weather Research and Forecasting (WRF) model and the

Lagrangian particle dispersion FLEXPART-WRF model. The most up-to-date ERA5 reanalysis

dataset is used as initial and boundary condition for the WRF model for every hour. Four experiments

were carried out to examine the sensitivity of simulation results to micro-physics parameterizations in

the WRF model with two configured domains of 5 km and 1 km horizontal resolution. Compared with

observation at Futaba and Naraha station, all experiments reproduce reasonably the variation of 137Cs

concentration from 11/03 to 26/03/2011. Statistical verification as shown in Taylor diagrams

highlights noticeable sensitivity of simulation results to different micro-physics choices. Three

configurations of the WRF model are also recommended for further study based on their better

performance among all.

Keywords: 137Cs dispersion, Fukushima Daiichi nuclear power plant, FLEXPART–WRF model,

ERA5 reanalysis data, Futaba, Naraha.

I. INTRODUCITON

The massive earthquake in Japan occurred

at 14:46 JST on 11/03/2011, with a magnitude of

9.0 [1] that caused heavy damage to infrastructure

along the east coast. It was followed by the

inundations of tsunami that caused power outages

and flooding in a large residential and industrial

area. This event had a major impact on five

nuclear power plants along Japan's northeast coast,

Higashidori, Onagawa, Fukushima Daiichi,

Fukushima Daini and Tokai Daini. Fig. 1 shows

the epicenter of the earthquake was far from

Fukushima Daiichi nuclear power plant (FDNPP)

180km in the northeast and Onagawa NPP 130km

in the east [2,3].

The FDNPP consists of six units that

were strongly impacted by the earthquake and

tsunami, leading to a serious nuclear accident,

radioactive substances were released from the

plant area and released into soil, water and air

environments (Fig. 2). The most serious is that

radioactive materials are released into the air,

they will be spreaded under different weather

conditions and can be fell in continent and sea

areas that is very far from the accident site.

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Nuclear Science and Technology - Volume 10, Number 3, September 2020
difference between the 
two measurement techniques is within ± 15%. 
This result is good and suitable for use in the 
two-phase flow experiment. 
B. Local time-averaged void fraction 
In order to present better local 
parameter distribution and transport 
characteristics, the results of bubbly flow test 
condition Run 4 is selected. The time-
averaged local void fraction and bubble 
velocity profiles at all three axial locations 
are given in Figure 7. Each row from top to 
bottom represents the result at L/D = 14.4, 
51.2 and 71.3, respectively. 
DINH ANH TUAN et al. 
55 
Fig. 6. Comparison of bubble velocity obtained by Imaging Technique and Conductivity Probe 
(a) (b) 
Fig. 7. Local profile of void fraction for run 4: jf = 1 m/s, jg = 0.05 m/s 
(a) Front Sensor; (b) Rear Sensor 
In Run 4, the void distribution 
experiences a change process of transition 
(flat) (L/D = 14.4) – wall peak (L/D = 51.2 and 
71.3). This reason is explained by the bubble 
breakup mechanism. At inlet position (L/D = 
14.4), wake entrainment mechanism is 
dominant, small bubbles coalescence to larger 
bubble, and drive bubbles toward pipe center. 
Along the flow path, the liquid velocity is high, 
and bubbles will be break up to smaller 
bubbles due to the turbulent effect and forced 
toward the wall by lift force, resulting in the 
wall peak void distribution. This bubble 
interaction mechanism also results in small 
amount change of void fraction at two upper 
axial positions. This phenomenon matches the 
measurement result in the work of Dang [5]. 
When the flow rate of gas is higher in 
run 9, the bubbles are fluctuated at the first 
EXPERIMENTAL INVESTIGATION OF HYDRODYNAMIC PHENOMENA IN 
56 
measurement position. Therefore, the void 
fraction at Front Sensor and Rear Sensor are 
quite different. Along the flow path, the 
bubble breakup to form smaller bubbles and 
concentrates at the wall region (Figure 8). 
Therefore, the void fraction in the wall region, 
at two upper measuring positions are higher 
than that of position measurement first. 
(a) (b) 
Fig. 8. Local profile of void fraction for run 9: jf = 1 m/s, jg = 0.1 m/s 
(a) Front Sensor; (b) Rear Sensor; 
(a) (b) 
Fig. 9. Local profile of void fraction for run 13: jf = 0.5 m/s, jg = 0.2 m/s 
(a) Front Sensor; (b) Rear Sensor; 
The local profiles of Run 13 are given in 
Figure. 9. In this flow condition, the major 
bubble shape is a slug and they cover the entire 
flow channel. Thus, group void distribution 
matches the shape of a slug bubble. However, 
under the same flow condition, the bubbly 
regime was recorded in previous study [15]. 
This experimental data was located near the 
boundary between bubbly and slug flow 
regime in Figure 5. Therefore, the difference 
can be explained by the fluctuation of air flow 
rate during the experiment, thus the flow 
regime was shifted from bubbly to slug flow. 
At the inlet position, bubbles coalescence to 
DINH ANH TUAN et al. 
57 
form larger bubbles. At second measuring 
position, the void distribution is affected by 
slug bubbles that small bubbles follow the slug 
bubbles, distributing in the slug bubbles’ wake 
regions. Besides, the effect of shear off 
mechanism starts to contribute to the number 
of small bubbles near-wall region. According 
to shear off mechanism, when slug bubbles are 
large enough, they are sheared at the rim, and 
many small bubbles show up. 
C. Bubble Velocity 
(a) (b) 
(c) 
Fig. 10. Local profile of bubble velocity: 
(a) Run 4; (b) Run 9; (c) Run 13 
In run 4 and run 9, the interfacial 
velocity is distributed corresponding to the 
single-phase velocity profile and this agrees 
with Hibiki [18]. The liquid velocity profile 
is flattened when the gas is added. As 
shown in Figure 10, the value of bubble 
velocity is approximately equal to the sum 
of superficial velocities. When bubbles 
enter the wake region, they will accelerate 
and may collide with the leading one. 
Therefore, the bubble velocity at first 
position is slightly higher than the two 
upper measuring positions. In addition, near 
to the wall region, the velocity of the 
bubbles is strongly fluctuated due to wall 
friction and turbulent intensity. 
EXPERIMENTAL INVESTIGATION OF HYDRODYNAMIC PHENOMENA IN 
58 
In Run 13, the channel-averaged velocity 
at the higher measuring positions are gradually 
decreased and are distributed almost uniformly 
in the radius. This phenomenon occurs in the 
case of low water superficial velocity, and drag 
force is domination. As the bubble grows, the 
bubble is normally accelerated by the effect of 
buoyancy force. However, due to the effect of 
drag force, velocity in run 13 is suitable. 
V. CONCLUSIONS 
The experimental investigation on local 
interfacial parameters for vertical upward air-
water two-phase flow was performed in this 
study. Two-sensor conductivity probe was used 
for the measurement of 25 flow conditions that 
covers from bubbly flow to slug flow. The 
local parameters included are a time-averaged 
void fraction and bubble interfacial velocity. 
The data acquisition frequency of 10 kHz and 
the sampling time of 60 s were applied. 
From the local experimental results, the 
profiles of void fraction and interfacial velocity 
along the axial and radial of the flow channel 
were discussed in detail. The bubble 
interaction mechanisms caused the differences 
in local parameter distribution. For high liquid 
superficial velocity (jf), the effect of buoyancy 
force is dominant, and bubble break up 
phenomena is observed. On the contrary, for 
low liquid superficial velocity (jf), the effect of 
drag force is dominant and bubble interaction 
mechanism will change from bubble break up 
to bubble coalescence. 
When changing the flow conditions, the 
void fraction distribution changes from wall 
peaking at Run 4 and Run 9 to center peak at 
Run 13. The reason might be due to the 
uncertainties in the measured results that need 
to be carefully considered and reduced in 
future works. In conclusion, the test facility, 
the experimental methods, and the preliminary 
experimental results obtained in this study can 
be helpful to study and comprehend the 
fundamental two-phase flow phenomena. For 
practical application in nuclear reactor safety, 
they are envisaged to be further improved and 
applied to verification and validation of 
calculation methods and codes, e.g., CFD 
codes, in modeling of two-phase flow. 
NOMENCLATURE 
D – pipe diameter 
g – acceleration of gravity 
L – length 
lchord – chord length 
N – number of bubble 
p – pressure 
t – time 
tdelay – delay time 
u – velocity 
V – Volume 
Greek Symbols 
α – void fraction 
µ – viscosity 
ρ – density 
σ – deviation standard 
Ω – total sampling time 
Subscripts 
b – bubble 
f – liquid 
g – gas 
ACKNOWLEDGEMENT 
This work was performed at Institute of 
Nuclear Science and Technology, Vietnam 
Atomic Energy Institute under the project 
“Construction of Thermal-hydraulic Experiment 
and Investigation of Hydrodynamic Phenomena 
of Two-phase Flow”, grant code 
DTCB.17/16/VKHKTHN. The authors would 
like to thank Ministry of Science and 
Technology for their support on this project. 
REFERENCES 
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Transfer And Two-Phase Flow (Series in 
DINH ANH TUAN et al. 
59 
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INSTRUCTIONS FOR AUTHORS 
GENERAL INFORMATION 
Nuclear Science and Technology (NST), an 
international journal of the Vietnam Atomic 
Energy Society (VAES) and Vietnam Atomic 
Energy Institute (VINATOM), quarterly publishes 
articles related to theory and application of nuclear 
science and technology. All papers and technical 
notes will be refereed. 
It is understood that the paper has been neither 
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elsewhere. The copyright of all published papers 
and notes will be transferred in VAES. 
DETAILED FIELDS 
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technology for peaceful utilization of nuclear 
energy and radiation. Authors should choose one 
of the following fields at the time they submit 
their manuscript: 1) Nuclear Physics, 2) Nuclear 
Data, 3) Reactor Physics, 4) Thermal Hydraulics, 
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Fuel and Materials, 8) Radioactive Waste 
Management, 9) Radiation Protection, 10) 
Radiation Technology, 11) Nuclear Techniques in 
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Radiotherapy, 13) Nuclear Techniques in 
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Isotope Hydrology, 16) Nuclear Analytical 
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E-mail: nuscitech@vinatom.gov.vn. 
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[1] C. Y. Fu et al., Nuclear Data for Science and 
Technology, S. M. Qaim (Ed.), p. 587 (1991). 
[2] C. Kalbach, Z. Phys, A283, 401 (1977). 
[3] S. Shibata, M. Imamura, T. Miyachi and M. 
Mutou, “Photonuclear spallation reactions in 
Cu”, Phys. Rev. C 35, 254 (1987). 
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