The improvement of thermal management action during the accident of nuclear power plants (NPPs) becomes important consideration including improving the inherent safety on NPPs for operation, especially in cooling process. The use of natural circulation as an alternative for thermal management and operating of NPPs, especially in SMRs becomes an interesting research and development topic of safety engineering. The leak of information related the characteristic of flow stability in natural circulation for use in passive safety system must be solved for implement this phenomenon in the real applications. Experimental method was used to determine the characteristic of natural circulation flow rate due to the temperature differences at two points. To clarify and understand the phenomenon, FASSIP-01 loop was constructed; with two parameters such as thermal-hydraulics represent by temperature and geometrical effect such as total pipe length, pipe diameter and height differences of cooler and heater. The purpose of the experiment is to understand the effect of power variation related into time respond from start-up until stable flow. The variations of heater power in this experiment are 3840 watt, 4240 watt, and 5928 watt with optimal cooling flow in secondary side (HSS flow) is 43.10 LPM and HSS flow variation from 21.57 LPM, 33.63 LPM and 43.10 LPM at heater power 5928 watt. The result of experiment shows It is show that, the effect only related to respond time for stability flow from instability flow. The increasing HSS flow in cooler area to respond time from 7325 s to 5041 s is more fast only 31.18%. In case of heater power increasing in heater area to respond time from 4855 s to 3857 s is more fast only 20.55%.

1.
Chang
,
M.H.
,
S.K.
Sim
, and
D.J.
Lee
,
SMART behaviour under over-pressurizing accident conditions
.
Nuclear Engineering and Design
,
2000
.
199
(
1
): p.
187
196
.
2.
Park
,
H.-S.
, et al,
Contribution of thermal–hydraulic validation tests to the standard design approval of SMART
.
Nuclear Engineering and Technology
,
2017
.
3.
Xia
,
G.
,
M.
Peng
, and
X.
Du
,
Calculation analysis on the natural circulation of a passive residual heat removal system for IPWR
.
Annals of Nuclear Energy
,
2014
.
72
: p.
189
197
.
4.
Hou
,
X.
,
Z.
Sun
, and
W.
Lei
,
Capability of RELAP5 code to simulate the thermal-hydraulic characteristics of open natural circulation
.
Annals of Nuclear Energy
,
2017
.
109
: p.
612
625
.
5.
Zou
,
J.
, et al,
Assessment of passive residual heat removal system cooling capacity
.
Progress in Nuclear Energy
,
2014
.
70
: p.
159
166
.
6.
Antariksawan
,
A. R.
 et al,
Numerical Study of Single Phase Natural Circulation Characteristics in a Passive Safety System Experimental Facility
.
IOP Conf. Series: Earth and Environmental Science
105
(
2017
)
012090
7.
Antariksawan
,
A. R.
 et al,
Simulation of Operational Conditions of FASSIP-02 Natural Circulation Cooling System Experimental Loop
,
Jurnal Sains dan Teknologi Nuklir Indonesia
, Vol.
19
, No.
1
(
2018
) p
41
54
.
8.
Anhar R.
Antariksawan
,
Surip
Widodo
,
Mulya
Juarsa
, Giarno,
M. Hadi
Kusuma
, and
Nandy
Putra
,
Preliminary investigation of natural circulation stability in FASSIP-01 experimental facility using RELAP5 code
,
AIP Conference Proceedings
2001
,
070003
(
2018
); .
9.
Yan
,
X.
,
G.
Fan
, and
Z.
Sun
,
Study on flow characteristics in an open two-phase natural circulation loop
.
Annals of Nuclear Energy
,
2017
.
104
: p.
291
300
.
10.
Juarsa
,
M.
, et al,
Preliminary Study on Mass Flow Rate in Passive Cooling Experimental Simulation During Transient Using NC-Queen Apparatus
,
Atom Indonesia
Vol.
40
, No.
3
, pp.
141
147
(
2014
).
11.
M.
Juarsa
,
J.P.
Witoko
, G Giarno,
D.
Haryanto
,
J.H.
Purba
,
An Experimental Analysis on Nusselt Number of Natural Circulation Flow in Transient Condition Based on the Height Differences between Heater and Cooler
,
Atom Indonesia
Vol.
44
, No.
3
, pp.XXX-XXX (
2018
); Article in press doi: .
12.
Juarsa
,
M.
, et al,
Passive System Simulation Facility (FASSIP) Loop for Natural Circulation Study
.
Proceeding of “Seminar Nasional Teknologi Energi Nuklir (SENTEN”. 2016
.
Batam
,
4-5 Agustus 2016
.
13.
Kim
,
Y.-S.
, et al,
Overview of the standard problems of the ATLAS facility.
Annals of Nuclear Energy
,
2014
.
63
: p.
509
524
.
14.
Wednesday
, August 16, 2017, at 14:15 pm]; Available from: https://www.psi.ch/teg/facilities.
15.
Kööp
,
K.
, et al,
Pre-test analysis for identification of natural circulation instabilities in TALL-3D facility.
Nuclear Engineering and Design
,
2017
.
314
: p.
110
120
.
16.
Juarsa
, et al,
Flow rate and temperature characteristics in steady state condition on FASSIP-01 loop during commissioning
,
Journal of Physics: Conference Series
962
(
1
) (
2017
),
012021
.
17.
Mulya
Juarsa
,
Anhar R.
Antariksawan
,
Surip
Widodo
,
M. Hadi
Kusuma
,
Agus Nur
Rohman
,
Giarno
, and
M. Hadid
Subki
,
Backward phenomenon on natural circulation flow based on power differences in FASSIP-01 loop
,
AIP Conference Proceedings
2001
,
050005
(
2018
); .
18.
Juarsa
,
M.
, et al,
Estimation of Natural Circulation Flow Based on Temperature in the FASSIP-02 Large-Scale Test Loop Facility
.
IOP Conf. Series: Earth and Environmental Science
105
(
2017
)
012091
.
This content is only available via PDF.