Abstract
The Moody and Henry–Fauske critical flow models implemented in Advanced Process Simulation Software (apros) have been validated against Marviken critical flow experiments and compared with other available simulations of the same experiments. Both models in combination with discharge coefficient 0.75 (suggested for best estimate calculations) produce results close to the experimental data for two-phase flows, while one-phase flow of subcooled water is underpredicted. Using discharge coefficient 1.0 for subcooled water leads to a good match with the experimental results, while two-phase flows become overpredicted.
Issue Section:
Special Papers
References
1.
Arnulfo
,
G.
,
Bertani
,
C.
, and
De Salve
,
M.
, 2014
, “
Prediction of Two-Phase Choked-Flow Through Safety Valves
,” J. Phys.: Conf. Ser.
,
501
, p. 012016
.10.1088/1742-6596/501/1/0120162.
De Lorenzo
,
M.
,
Lafon
,
P.
,
Seynhaeve
,
J.-M.
, and
Bartosiewicz
,
Y.
, 2017
, “
Benchmark of Delayed Equilibrium Model (Dem) and Classic Two-Phase Critical Flow Models Against Experimental Data
,” Int. J. Multiphase Flow
,
92
, pp. 112
–130
.10.1016/j.ijmultiphaseflow.2017.03.0043.
Kim
,
Y.-S.
, 2015
, “
Critical Flow Maps Using an Extended Henry–Fauske Model
,” Ann. Nucl. Energy
,
75
, pp. 516
–520
.10.1016/j.anucene.2014.08.0704.
Porkholm
,
K.
,
Honkoila
,
K.
,
Nurmilaukas
,
P.
, and
Kontio
,
H.
, 1997
, “
APROS Multifunctional Simulator for Thermal and Nuclear Power Plants
,” World Congress on Systems Simulation–97
,
Society for Computer Simulation Europe and Society for Computer Simulation International
,
Singapore
, Sept. 1–3, pp. 504
–508
.5.
Pana
,
P.
, and
Müller
,
M.
, 1978
, “
Subcooled and Two Phase Critical Flow States and Comparison With Data
,” Nucl. Eng. Des.
,
45
(1
), pp. 117
–125
.10.1016/0029-5493(78)90110-36.
Henry
,
R. E.
, and
Fauske
,
H. K.
, 1971
, “
The Two-Phase Critical Flow of One-Component Mixtures in Nozzles, Orifices, and Short Tubes
,” ASME J. Heat Transfer
,
93
(2
), pp. 179
–187
.10.1115/1.34497827.
Moody
,
F. J.
, 1965
, “
Maximum Flow Rate of a Single Component, Two-Phase Mixture
,” ASME J. Heat Transfer
,
87
(1
), pp. 134
–141
.10.1115/1.36890298.
U.S.NRC
, 1975
, Appendix K to Part 50 - ECCS Evaluation Models, 10 CFR Part 50, NRC Regulation
, U.S. Nuclear Regulatory Commission
, Washington, DC
.https://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-appk.html9.
Fjaestad
,
M.
, and
Jonter
,
T.
, 2010
, Between Welfare and Warfare: The Rise and Fall of the ‘Swedish Line’
,
Science History Publications
, Stockholm, Sweden
.10.
Wikdahl
,
C.-E.
, 2007
, “
Marvikenreaktor - Ett Industripolitiskt Utvecklingsprojekt i Otakt Med Tiden
,”
Swedish Nuclear Power Inspectorate
, Stockholm, Sweden
, Report No. SKI 2007:18.
11.
Risø National Laboratory
, 1977
, “
The Marviken Full Scale Containment Experiments: Summary Report
,” Risø National Laboratory
, Roskilde, Denmark
, Report No. MXA-0-402.12.
Gauvain
,
J.
, and
Lhiaubet
,
G.
, 1986
, “
Marviken Aerosol Transport Tests (ATT). Description of the Experiments and Results
,” International Atomic Energy Agency
, Vienna, Austria
.13.
Multinational Project,
1979
, “
The Marviken Full Scale Critical Flow Tests—Summary Report
,” Marviken Power Station
, Studsvik, Sweden
, Report No. MXC-301.
14.
Multinational Project,
1979
, “
The Marviken Full Scale Critical Flow Tests—Description of the Test Facility
,” Marviken Power Station
, Studsvik, Sweden
, Report No. MXC-101.
15.
Multinational Project,
1979
, “
The Marviken Full Scale Critical Flow Tests—Results From Test 15
,” Marviken Power Station
, Studsvik, Sweden
, Report No. MXC-215.
16.
Multinational Project,
1979
, “
The Marviken Full Scale Critical Flow Tests—Results From Test 20
,” Marviken Power Station
, Studsvik, Sweden
, Report No. MXC-220
.17.
Multinational Project,
1979
, “
The Marviken Full Scale Critical Flow Tests—Results From Test 21
,” Marviken Power Station
, Studsvik, Sweden
, Report No. MXC-221
.18.
Multinational Project,
1979
, “
The Marviken Full Scale Critical Flow Tests—Results From Test 22
,” Marviken Power Station
, Studsvik, Sweden
, Report No. MXC-222
.19.
Multinational Project,
1979
, “
The Marviken Full Scale Critical Flow Tests—Results From Test 23
,” Marviken Power Station
, Studsvik, Sweden
, Report No. MXC-223.
20.
Sokolowski
,
L.
, and
Kozlowski
,
T.
, 2012
, “
Assessment of Two-Phase Critical Flow Models Performance in RELAP5 and TRACE against Marviken Critical Flow Tests
,”
U.S.NRC
, Washington, DC
, Report No. NUREG/IA-0401.21.
Wijkström
,
H.
, 1997
, “
Anvisning för Beräkning av Brottflöden vid Nödkylningsanalys, Bestämning av Reaktionskrafter och Bestämning av Byggnadsbelastningar
,”ABB Atom AB
, Västerås, Sweden
, Report No. PA 97-165.
22.
Tesinsky
,
M.
,
Wäng
,
J.
, and
Bredolt
,
U.
, 2016
, “
Validation of the HEM and Moody Critical Flow Models in POLCA-T
,” The Physics of Reactors (PHYSOR)
,
American Nuclear Society
,
Sun Valley, ID
.Copyright © 2020 by ASME
You do not currently have access to this content.