DIONISIO is a computer code designed to simulate the behavior of one nuclear fuel rod during its permanence within the reactor. Starting from the power history and the external conditions to which the rod is subjected, the code predicts all the meaningful variables of the system. Its application range has been recently extended to include accidental conditions, in particular the so-called loss of coolant accidents (LOCA). In order to make realistic predictions, the conditions in the rod environment have been taken into account since they represent the boundary conditions with which the differential equations describing the fuel phenomena are solved. Without going into the details of the thermal-hydraulic modeling, which is the task of the specific codes, a simplified description of the conditions in the cooling channel during a LOCA event has been developed and incorporated as a subroutine of DIONISIO. This has led to an improvement of the fuel behavior simulation, which is evidenced by the considerable number of comparisons with experiments carried out, many of them reported in this paper. Moreover, this work describes a model of high temperature capture and release of hydrogen in the nuclear fuel cladding, in scenarios typical of LOCA events. The corresponding computational model is being separately tested and will be next included in the DIONISIO thermal-hydraulic module.

References

1.
Soba
,
A.
, and
Denis
,
A.
,
2015
, “
DIONISIO 2.0: New Version of the Code for Simulating a Whole Nuclear Fuel Rod Under Extended Irradiation
,”
Nucl. Eng. Des.
,
292
, pp.
213
221
.
2.
Soba
,
A.
,
Denis
,
A.
,
Romero
,
L.
,
Villarino
,
E.
, and
Sardella
,
F.
,
2013
, “
A High Burn-Up Model Developed for the DIONISIO Code
,”
J. Nucl. Mater.
,
433
(
1–3
), pp.
160
166
.
3.
Soba
,
A.
,
Lemes
,
M.
, and
Denis
,
A.
,
2015
, “
An Empirical Formulation to Describe the Evolution of the High Burnup Structure
,”
J. Nucl. Mater.
,
456
, pp.
174
181
.
4.
Soba
,
A.
,
Lemes
,
M.
,
González
,
M. E.
,
Denis
,
A.
, and
Romero
,
L.
,
2014
, “
Simulation of the Behavior of Nuclear Fuel Under High Burnup Conditions
,”
Ann. Nucl. Energy
,
70
, pp.
147
156
.
5.
Manngard
,
T.
,
Jernkvist
,
L. O.
, and
Massih
,
A.
,
2011
, “
Evaluation of Loss-of-Coolant Accident Simulation Tests With the Fuel Rod Analysis Code FRAPTRAN-1.4
,” HI TEMP 2011 Conference, Boston, MA, Sept. 20–22.
6.
Rosinger
,
H. E.
,
1984
, “
A Model to Predict the Failure of Zircaloy-4 Fuel Sheathing During Postulated LOCA Conditions
,”
J. Nucl. Mater.
,
120
(
1
), pp.
41
54
.
7.
Ragheb
,
M.
,
2011
, “
Decay Heat Generation in Fission Reactors
,”
Course of Nuclear, Plasma and Radiological Engineering
, University of Illinois at Urbana-Champaign, Champaign, IL, Chap. 8.
8.
Delette
,
G.
, and
Charles
,
M.
,
1997
, “
Thermal Conductivity of Fully Dense Unirradiated UO2: A New Formulation From Experimental Results Between 100 °C and 2500 °C and Associated Fundamental Properties, Water Reactor Fuel Element Modeling at High Burnup and Its Experimental Support
,” International Atomic Energy Agency, Vienna, Austria, Report, No. IAEA–TECDOC–957.
9.
Fink
,
J. K.
, and
Leibowitz
,
L.
,
1995
, “
Thermal Conductivity of Zirconium
,”
J. Nucl. Mater.
,
226
(
1–2
), pp.
44
50
.
10.
Vojtek
,
I.
,
1986
, “Heat Transfer Processes During Intermediate and Large Break Loss-of-Coolant Accidents (LOCAs),” U.S. Nuclear Regulatory Commission, Washington, DC, International Agreement Report, NUREG/IA-0002.
11.
Mochizuki
,
H.
,
2009
, “
Thermal Hydraulics in Nuclear Reactors, International Graduate Course
,” Tokyo Institute of Technology, Tokyo, Japan, Report No. 13:20-14:50.
12.
Odar
,
F.
,
2001
, “
Assessment of the TRAC-M Codes Using Flecht-Seaset Reflood and Steam Cooling Data
,” U.S. Nuclear Regulatory Commission, Washington, DC, Report No. NUREG-1744.
13.
Todreas
,
N.
, and
Kazimi
,
M.
,
1989
,
Nuclear Systems
(
Thermal Hydraulic Fundamentals
, Vol.
1
), Massachusetts Institute of Technology,
Cambridge, MA
.
14.
Chen
,
Y.
,
2012
, “
An Overview of Heat Transfer Phenomena
,” Critical Heat Flux in Subcooled Flow Boiling of Water, IntechOpen, Rijeka, Croatia, Chap. 9.
15.
Tong
,
L. S.
, and
Weisman
,
J.
,
1966
,
Thermal Analysis of Pressurized Water Reactors
,
American Nuclear Society
,
LaGrange Park, IL
, Chap. 4.
16.
Kolev
,
N. I.
,
2005
,
Multiphase Flow Dynamics 2: Thermal and Mechanical Interactions
,
Springer-Verlag
,
Berlin
.
17.
Ramu
,
K.
, and
Weisman
,
J.
,
1977
, “
Transition Flow Boiling Heat Transfer to Water in a Vertical Annulus
,”
Nucl. Eng. Des.
,
40
(
2
), pp.
285
295
.
18.
Lemes
,
M.
,
Soba
,
A.
,
Daverio
,
H.
, and
Denis
,
A.
,
2017
, “
Inclusion of Models to Describe Severe Accident Conditions in the Fuel Simulation Code DIONISIO
,”
Nucl. Eng. Des.
,
315
, pp.
1
10
.
19.
Hagrman
,
D.
,
Reymann
,
G.
, and
Mason
,
R.
,
1979
, “
MATPRO Version 11: A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Behavior
,” Idaho National Engineering Laboratory, Idaho Falls, ID, Technical Report No. NUREG/CR-0497.
20.
Cathcart
,
J. V.
,
Pawel
,
R. E.
,
McKee
,
R. A.
,
Druschel
,
R. E.
,
Yurek
,
G. J.
,
Campbell
,
J. J.
, and
Jury
,
S. H.
,
1977
, “
Zirconium Metal-Water Oxidation Kinetics—IV: Reaction Rate Studies
,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No. ORNL/NUREG-17.
21.
Veshchunov
,
M.
, and
Berdyshev
,
A.
,
1998
, “
Modelling of Hydrogen Absorption by Zirconium Alloys During High Temperature Oxidation in Steam
,”
J. Nucl. Mater.
,
255
(
2–3
), pp.
250
262
.
22.
Cox
,
B.
,
1976
, “
Oxidation of Zirconium and Its Alloys
,”
Advances in Corrosion Science and Technology
, Vol.
5
, Springer, Boston, MA, pp.
173
391
.
23.
Veshchunov
,
M. S.
, and
Shestak
,
V. E.
,
2015
, “
Modeling of Zr Alloy Burst Cladding Internal Oxidation and Secondary Hydriding Under LOCA Conditions
,”
J. Nucl. Mater.
,
461
, pp.
129
142
.
24.
Cox
,
B.
,
1985
, “
Mechanisms of Hydrogen Absorption by Zirconium Alloys
,” Atomic Energy of Canada Limited, Chalk River, ON, Canada, Report No. AECL-8702.
25.
Adamson
,
R.
,
Garzarolli
,
F.
,
Cox
,
B.
,
Strasser
,
A.
, and
Rudling
,
P.
,
2007
, “
Corrosion Mechanisms in Zirconium Alloys
,”
Advanced Nuclear Technology International
,
Skultuna, Sweden
.
26.
Olander
,
D. R.
,
1994
, “
Materials Chemistry and Transport Modelling for Severe Accident Analysis in Light-Water Reactors—I: External Cladding Oxidation
,”
Nucl. Eng. Des.
,
148
(
2–3
), pp.
253
271
.
27.
Wang
,
W.
, and
Olander
,
D. R.
,
1992
, “
Thermochemistry of the U-0 and Zr-0 Systems
,” U.S. Department of Energy, Washington, DC.
28.
Moalem
,
M.
, and
Olander
,
D. R.
,
1991
, “
The High-Temperature Solubility of Hydrogen in Pure and Oxygen-Containing Zircaloy
,”
J. Nucl. Mater.
,
178
(
1
), pp.
61
72
.
29.
Grosse
,
M.
,
Steinbrück
,
M.
,
Lehmann
,
E.
, and
Vontobel
,
P.
,
2008
, “
Kinetics of Hydrogen Absorption and Release in Zirconium Alloys During Steam Oxidation
,”
Oxid. Met.
,
70
(
3–4
), pp.
149
162
.
30.
Steinbrück
,
M.
,
2004
, “
Hydrogen Absorption by Zirconium Alloys at High Temperatures
,”
J. Nucl. Mater.
,
334
(
1
), pp.
58
64
.
31.
Park
,
K.
, and
Olander
,
D. R.
,
1991
, “
Hydrogen Dissolution in and Release From Nonmetals: III Tetragonal Zirconia
,”
J. Am. Ceram. Soc.
,
74
(
1
), pp.
72
77
.
32.
Veshchnov
,
M.
, and
Shestak
,
V.
,
2012
, “
Models for Hydrogen Uptake and Release Kinetics by Zirconium Alloys at High Temperatures
,”
Nucl. Eng. Des.
,
252
, pp.
96
107
.
33.
Frecska
,
J.
,
Konczos
,
G.
,
Maróti
,
L.
, and
Matus
,
L.
,
1995
, “
Oxidation and Hydriding of Zrl%Nb Alloys by Steam at 900-1200 °C
,” KFKI Atomic Energy Research Institute, Budapest, Hungary, Report No. 17/G.
34.
Ek
,
M.
,
2005
, “
LOCA Testing at Halden; the Second Experiment IFA-650.2, HWR-813
,” Halden, Norway.
35.
Szabados
,
L.
,
Ezsöl
,
G.
,
Perneczky
,
L.
,
Krepper
,
E.
,
Prasser
,
H.
, and
Schäfer
,
F.
,
1995
, “Two Phase Flow Behavior During a Medium Size Cold Leg LOCA Test on PMK-2 (IAEA SPE-4),”
KFKl Atomic Energy Research Institute
,
Budapest, Hungary
.
36.
Stuckert
,
J.
,
Grosse
,
M.
,
Rössger
,
C.
,
Steinbrück
,
M.
, and
Walter
,
M.
,
2011
, “Results of the LOCA Reference Bundle Test QUENCH-L0 With Zircaloy-4 Claddings,”
Karlsruhe Institut für Technologie
,
Karlsruhe, Germany
.
37.
Hollands
,
T.
,
Bals
,
C.
, and
Austregesilo
,
H.
,
2011
, “
Simulation of QUENCH-L0 With ATHLET-CD
,” International Quench Workshop, Karlsruhe, Germany, Nov. 22–24.
You do not currently have access to this content.