Abstract

CATHENA has been successfully employed to simulate accident and startup transients in the development of the Canadian supercritical water reactor concept. This success is attributed to the implementation of a novel method to integrate supercritical modeling elements into the code. A supercritical water properties scheme was used that does not rely on the use of pseudo-phases and treats the supercritical regime as a single uninterrupted phase. The development of a robust numerical strategy manages the transitions that can occur in accident scenarios. Finally, the utilization of an expanded transcritical heat transfer look-up-table that smoothly transitions across the near-critical and supercritical regions over a wide temperature range ensures consistent, stable simulation results.

References

1.
Hanna
,
B. N.
,
1998
, “
CATHENA: A Thermalhydraulic Code for CANDU Analysis
,”
Nucl. Eng. Des.
,
180
(
2
), pp.
113
131
.10.1016/S0029-5493(97)00294-X
2.
Riemke
,
R. A.
,
Davis
,
C. B.
, and
Schultz
,
R. R.
,
2003
, “
RELAP5-3D Code for Supercritical-Pressure, Light-Water-Cooled Reactors
,”
11th International Conference on Nuclear Engineering
,
ASME
Paper No. ICONE11-36125.10.1115/ICONE11-36125
3.
Antoni
,
O.
, and
Dumaz
,
P.
,
2003
, “
Preliminary Calculations of a Supercritical Light Water Reactor Concept Using the CATHARE Code
,”
Proceedings of ICAPP'03, Cordoba
, Spain, May 4–7, Paper No. 3146.
4.
Dumaz
,
P.
, and
Antoni
,
O.
,
2003
, “
The Extension of the CATHARE2 Computer Code Above the Critical Point, Applications to a Supercritical Light Water Reactor
,”
The Tenth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10)
, Seoul, Korea, Oct. 5–9.
5.
Fu
,
S. W.
,
Liu
,
X. J.
,
Zhou
,
C.
,
Xu
,
Z. H.
,
Yang
,
Y. H.
, and
Cheng
,
X.
,
2012
, “
Modification and Application of the System Analysis Code ATHLET to Trans-Critical Simulations
,”
Ann. Nucl. Energy
,
44
, pp.
40
49
.10.1016/j.anucene.2012.02.005
6.
Zhou
,
C.
,
Yang
,
Y.
, and
Cheng
,
X.
,
2012
, “
Feasibility Analysis of the Modified ATHLET Code for Supercritical Water Cooled Systems
,”
Nucl. Eng. Des.
,
250
, pp.
600
612
.10.1016/j.nucengdes.2012.06.021
7.
Liu
,
X. J.
,
Yang
,
T.
, and
Cheng
,
X.
,
2014
, “
Development of Sub-Channel/System Coupled Code and Its Application to a Supercritical Water-Cooled Test Loop [ATHLET]
,”
The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10)
, Okinawa, Japan, Dec. 14–18.
8.
Hänninen
,
M.
, and
Kurki
,
J.
,
2008
, “
Simulation of Flows at Supercritical Pressures With a Two-Fluid Code [APROS]
,”
NUTHOS-7: The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
, Operation and Safety, Seoul, Korea, Oct. 5–9.
9.
Beuthe
,
T.
, and
Vasić
,
A.
,
2007
, “
Application of HLWP Supercritical Light Water Properties in CATHENA
,”
28th Annual CNS Conference
, Saint John, NB, Canada, June 3–6.
10.
Wagner
,
W.
, and
Pruß
,
A.
,
2002
, “
The IAPWS Formulation 1995 for the Thermodynamic Properties of Ordinary Water Substance for General and Scientific Use
,”
J. Phys. Chem. Ref. Data
,
31
(
2
), pp.
387
535
.10.1063/1.1461829
11.
Dittus
,
F. W.
, and
Boelter
,
L. M. K.
,
1985
, “
Heat Transfer in Automobile Radiators of the Tubular Type
,”
Int. Commun. Heat Mass Transfer
,
12
(
1
), pp.
3
22
.10.1016/0735-1933(85)90003-X
12.
Chen
,
J. C.
,
1966
, “
Correlation for Boiling Heat Transfer to Saturated Fluids in Convective Flow, I and EC
,”
Process Des. Dev.
,
5
(
3
), pp.
322
329
.10.1021/i260019a023
13.
Bishop
,
A.
,
Sandberg
,
R.
, and
Tong
,
L.
,
1964
,
Forced Convection Heat Transfer to Water at Near-critical Temperatures and Supercritical Pressures
, Westinghouse Electric Corporation, Atomic Power Division, Pittsburgh, PA, Report No. WCAP-2056.
14.
Jackson
,
J. D.
,
2002
, “
Considerations of the Heat Transfer Properties of Supercritical Pressure Water, in Connection With the Cooling of Advanced Nuclear Reactors
,”
Proceedings of the 13th Pacific Basin Nuclear Conference
, Shenzhen City, China, Oct. 21–25.
15.
Mokry
,
S.
,
Farah
,
F.
,
King
,
K.
,
Gupta
,
S.
, and
Pioro
,
I.
,
2009
, “
Development of Supercritical Water Heat-Transfer Correlation for Vertical Bare Tubes
,”
Proceedings of the Nuclear Energy for New Europe 2009 International Conference
,
P.
Kirillov
, ed., Bled, Slovenia, Sept. 14–17, Paper No. 210.
16.
Yuan
,
L. Q.
,
Dominguez
,
A. N.
, and
Yang
,
J.
,
2014
, “
Heat Transfer Correlation for Fuel Bundles of the Canadian Supercritical Water Cooled Reactor in Normal Heat Transfer Conditions
,” Atomic Energy of Canada, Chalk River, ON, Canada, Report No. 217-125000-440-007.
17.
Zahlan
,
H.
,
Tavoularis
,
S.
, and
Groeneveld
,
D. C.
,
2015
, “
A Look Up Table for Trans Critical Heat Transfer in Water Cooled Tubes
,”
Nucl. Eng. Des.
,
285
, pp.
109
125
.10.1016/j.nucengdes.2014.12.027
18.
HuangGaudet
,
X.
,
Yetisisr
,
M. M.
,
Wang
,
D. F.
, and
Wang
,
S.
,
2014
, “
Analysis of Passive Residual Heat Removal Systems for the Canadian Supercritical Water-Cooled Reactor
,”
2014 Canada-China Conference on Advanced Reactor Development (CCCARD-2014)
, Niagara Falls Marriott Hotel, Niagara Falls, ON, Canada, Paper No. CCCARD2014-019.
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