A one-dimensional theoretical model has been used to analyze the steady state and stability performance of a single-phase, two-phase, and supercritical natural circulation in a uniform diameter rectangular loop. Parametric influences of diameter, inlet temperature, and system pressure on the steady state and stability performance have been studied. In the single-phase liquid filled region, the flow rate is found to increase monotonically with power. On the other hand, the flow rate in two-phase natural circulation systems is found to initially increase, reach a peak, and then decrease with power. For the supercritical region also, the steady state behavior is found to be similar to that of the two-phase region. However, if the heater inlet temperature is beyond the pseudo critical value, then the performance is similar to single-phase loops. Also, the supercritical natural circulation flow rate decreases drastically during this condition. With an increase in loop diameter, the flow rate is found to enhance for all the three regions of operation. Pressure has a significant influence on the flow rate in the two-phase region, marginal effect in the supercritical region, and practically no effect in the single-phase region. With the increase in loop diameter, operation in the single-phase and supercritical regions is found to destabilize, whereas the two-phase loops are found to stabilize. Again, pressure has a significant influence on stability in the two-phase region.

1.
Delmastro
,
D. F.
, 2000, “
Thermal-Hydraulic Aspects of CAREM Reactor
,”
Proceedings of the IAEA Technical Committee Meeting on Natural Circulation Data and Innovative Nuclear Power Plant Design
, July 18–21, Vienna, Austria.
2.
Samoilov
,
O. B.
, and
Kurachenkov
,
A. V.
, 1997, “
Nuclear District Heating Plants AST-500: Present Status and Prospects for Future in Russia
,”
Nucl. Eng. Des.
0029-5493,
173
, pp.
109
117
.
3.
Dazhong
,
W.
,
Zuying
,
G.
, and
Wenxiang
,
Z.
, 1993, “
Technical Design Features and Safety Analysis of the 200 MWt Nuclear Heating Reactor
,”
Nucl. Eng. Des.
0029-5493,
143
, pp.
1
7
.
4.
Sinha
,
R. K.
, and
Kakodkar
,
A.
, 2006, “
Design and Development of the AHWR—The Indian Thorium Fuelled Innovative Nuclear Reactor
,”
Nucl. Eng. Des.
0029-5493,
236
, pp.
683
700
.
5.
Kuznetsov
,
Y. N.
,
Romenkov
,
A. A.
,
Alekseev
,
A. I.
,
Lisitsa
,
F. D.
,
Tokarev
,
Y. I.
, and
Yarmolenko
,
O. A.
, 2001, “
NPP With VK-300 Boiling Water Reactor for Power and District Heating Grids
,”
Proceedings of the International Seminar on Small and Medium Sized Reactors: Status and Prospects Organized by IAEA
, Cairo, Egypt, May 27–31, Paper No. IAEA-SR-218/32.
6.
Bushby
,
S. J.
,
Dimmick
,
G. R.
,
Duffey
,
R. B.
,
Spinks
,
N. J.
,
Burrill
,
K. A.
, and
Chan
,
P. S. W.
, 2000, “
Conceptual Designs for Advanced, High-Temperature CANDU Reactors
,”
Proceedings of the SCR-2000
, Nov. 6–8, Tokyo, Japan.
7.
Silin
,
V. A.
,
Voznesensky
,
V. A.
, and
Afrov
,
A. M.
, 1993, “
The Light Water Integral Reactor With Natural Circulation of the Coolant at Supercritical Pressure B-500 SKDI
,”
Nucl. Eng. Des.
0029-5493,
144
, pp.
327
336
.
8.
Vijayan
,
P. K.
, 2002, “
Experimental Observations on the General Trends of the Steady State and Stability Behavior of Single-Phase Natural Circulation Loops
,”
Nucl. Eng. Des.
0029-5493,
215
, pp.
139
152
.
9.
Nayak
,
A. K.
,
Vijayan
,
P. K.
,
Saha
,
D.
,
Venkat Rap
,
V.
, and
Aritomi
,
M.
, 1998, “
Linear Analysis of Thermo-Hydraulic Instabilities of the Advanced Heavy Water Reactor (AHWR)
,”
J. Nucl. Sci. Technol.
0022-3131,
35
, pp.
768
778
.
10.
Sharma
,
M.
,
Pilkhwal
,
D. S.
,
Vaidya
,
A. M.
,
Jana
,
S. S.
,
Vijayan
,
P. K.
, and
Saha
,
D.
, 2008, “
Heat Transfer, Pressure Drop and Stability Studies for Supercritical Natural Circulation Systems
,” Annual Progress Report on the IAEA CRP on Heat transfer, Pressure Drop and Stability Studies for Supercritical Natural Circulation Systems, Research Contract No. 14344.
11.
Gartia
,
M. R.
,
Vijayan
,
P. K.
, and
Pilkhwal
,
D. S.
, 2006, “
A Generalized Flow Correlation for Two-Phase Natural Circulation Loops
,”
Nucl. Eng. Des.
0029-5493,
236
, pp.
1800
1809
.
12.
Vijayan
,
P. K.
,
Nayak
,
A. K.
,
Pilkhwal
,
D. S.
,
Saha
,
D.
, and
Venkat Rap
,
V.
, 1992, “
Effect of Loop Diameter on the Stability of Single-Phase Natural Circulation in Rectangular Loops
,”
Proceedings of the Fifth International Topical Meeting on Reactor Thermalhydraulics, NURETH-5
, Salt Lake City, UT, Sept. 21–24, Vol.
1
, pp.
261
267
.
13.
Vijayan
,
P. K.
,
Nayak
,
A. K.
,
Saha
,
D.
, and
Gartia
,
M. R.
, 2008, “
Effect of Loop Diameter on the Steady State and Stability Behaviour of Single-Phase and Two-Phase Natural Circulation Loops
,”
Science and Technology of Nuclear Installations
,
2008
, Article ID
672704
.
You do not currently have access to this content.