In a natural circulation boiling water reactor (BWR), the core power varies in both axial and radial directions inside the reactor core. The variation along the axial direction is more or less constant throughout the reactor; however, there exists variation of reactor power in the radial direction. The channels located at the periphery have low power compared to the center of the core and are equipped with orifices at their inlet. This creates nonuniformity in the radial direction in the core. This study has been performed in order to understand the effect of this radial variation of power on the stability characteristics of the reactor. Four channels of a pressure tube type natural circulation BWR have been considered. The reactor has been modeled using RELAP5/MOD3.2. Before using the model, it was first benchmarked with experimental measurements and then the characteristics of both low power and high power oscillations, respectively, known as type-I and type-II instability, have been investigated. It was observed that the type-I instability shows slight destabilizing effect of increase in power variation among different channels. However, in the case of type-II instability, it was found out that the oscillations get damped with an increase in power variation among the channels. A similar effect was found for the presence of orifices at the inlet in different channels. However, the increase in number of orificed channels showed stabilizing effect for both type-I and type-II instabilities.

References

1.
Sinha
,
R. K.
, and
Kakodkar
,
A.
,
2006
, “
Design and Development of the AHWR—The Indian Thorium Fuelled Innovative Nuclear Reactor
,”
Nucl. Eng. Des.
,
236
(
7–8
), pp.
683
700
.
2.
Podowski
,
M. Z.
,
Lahey
,
R. T.
, Jr.
,
Clausse
,
A.
, and
Desanctis
,
N.
,
1990
, “
Modeling and Analysis of Channel-to-Channel Instabilities in Boiling Systems
,”
Chem. Eng. Commun.
,
93
(
1
), pp.
75
92
.
3.
Aritomi
,
M.
,
Aoki
,
S.
, and
Inoue
,
A.
,
1977
, “
Instabilities in Parallel Channel of Forced-Convection Boiling Upflow System—II: Experimental Results
,”
J. Nucl. Sci. Technol.
,
14
(
2
), pp.
88
96
.
4.
March-Leuba
,
J.
,
1990
, “
Radial Nodalization Effects on BWR Stability Calculations
,” International Workshop on BWR Stability, Brookhaven, NY, Oct. 17--19, Paper No.
CONF-9010224-2
.http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/22/019/22019509.pdf
5.
Kumar
,
A.
, and
Srivenkatesan
,
R.
,
1984
, “
Nodal Expansion Method for Reactor Core Calculations
,” Bhabha Atomic Research Centre, Bombay, India, Report No.
BARC-1249
https://inis.iaea.org/search/search.aspx?orig_q=RN:16064505.
6.
Chandraker
,
D. K.
,
Maheshwari
,
N. K.
,
Saha
,
D.
, and
Sinha
,
R. K.
,
2002
, “
A Computer Code for Thermal Hydraulic Analysis of a Natural Circulation Reactor
,”
Fifth ISHMT-ASME Heat and Mass Transfer Conference
, Kolkata, India, Jan. 3–5, Paper No. HMT-2002-C149.
7.
The RELAP5 Code Development Team
,
1995
, “
RELAP5/MOD3 Code Manual Volume II: User's Guide and Input Requirements
,” Idaho National Engineering Laboratory, Idaho Falls, ID, Report, No.
INEL-95/0174
.https://www.nrc.gov/docs/ML1103/ML110330252.pdf
8.
Jain
,
V.
,
Nayak
,
A. K.
,
Vijayan
,
P. K.
,
Saha
,
D.
, and
Sinha
,
R. K.
,
2010
, “
Experimental Investigation on the Flow Instability Behavior of a Multi-Channel Boiling Natural Circulation Loop at Low-Pressures
,”
Exp. Therm. Fluid Sci.
,
34
(
6
), pp.
776
787
.
9.
Fukuda
,
K.
, and
Kobori
,
T.
,
1979
, “
Classification of Two-Phase Flow Instability by Density Wave Oscillation Model
,”
J. Nucl. Sci. Technol.
,
16
(
2
), pp.
95
108
.
10.
Reactor Design and Development Group,
2009
, “
Inputs for Safety Analysis and Detailed Design of AHWR Major Systems
,” Bhabha Atomic Research Centre, Mumbai, India, Report No. AHWR/USI/0151/001.
11.
Singh
,
S.
,
Nayak
,
A. K.
, and
Aparna
,
J.
,
2016
, “
Experimental Investigation on Characteristics of Boiling Two-Phase Flow Instability in a Parallel-Multichannel Natural Circulation System
,”
Nucl. Sci. Eng.
,
184
(
2
), pp.
263
279
.
12.
Fukuda
,
K.
, and
Hasegawa
,
S.
,
1979
, “
Analysis on Two-Phase Flow Instability in Parallel Multichannels
,”
J. Nucl. Sci. Technol.
,
16
(
3
), pp.
190
199
.
You do not currently have access to this content.