An ex-vessel steam explosion may occur when, during a severe reactor accident, the reactor pressure vessel fails and the molten core pours into the water in the reactor cavity. A steam explosion is a fuel-coolant interaction process where the heat transfer from the melt to water is so intense and rapid that the timescale for heat transfer is shorter than the timescale for pressure relief. This can lead to the formation of shock waves and production of missiles that may endanger surrounding structures. A strong enough steam explosion in a nuclear power plant could jeopardize the containment integrity and so lead to a direct release of radioactive material to the environment. In the article, different scenarios of ex-vessel steam explosions in a typical pressurized water reactor cavity are analyzed with the code MC3D, which is being developed for the simulation of fuel-coolant interactions. A comprehensive parametric study was performed by varying the location of the melt release (central and side melt pours), the cavity water subcooling, the primary system overpressure at vessel failure, and the triggering time for explosion calculations. The main purpose of the study was to determine the most challenging ex-vessel steam explosion cases in a typical pressurized water reactor and to estimate the expected pressure loadings on the cavity walls. Special attention was given to melt droplet freezing, which may significantly influence the outcome of the fuel-coolant interaction process. The performed analysis shows that for some ex-vessel steam explosion scenarios much higher pressure loads are predicted than obtained in the OECD program SERENA Phase 1.

1.
Berthoud
,
G.
, 2000, “
Vapour Explosions
,”
Annu. Rev. Fluid Mech.
0066-4189,
32
, pp.
573
611
.
2.
Magallon
,
D.
,
Bang
,
K. H.
,
Basu
,
S.
,
Berthoud
,
G.
,
Bürger
,
M.
,
Corradini
,
M. L.
,
Jacobs
,
H.
,
Meignen
,
R.
,
Melikhov
,
O.
,
Moriyama
,
K.
,
Naitoh
,
M.
,
Song
,
J. H.
,
Suh
,
N.
, and
Theofanous
,
T. H.
, 2005, “
Results of Phase 1 of OECD Programme SERENA on Fuel-Coolant Interaction
,”
ERMSAR-2005
, Aix-en-Provence, France, pp.
1
12
.
3.
Meignen
,
R.
, and
Picchi
,
S.
, 2005, “
MC3D Version 3.5: User’s Guide
,” IRSN Report No. NT/DSR/SAGR/05-84.
4.
Meignen
,
R.
, 2005, “
Status of the Qualification Program of the Multiphase Flow Code MC3D
,”
Proceedings of ICAPP ’05
, Seoul, Korea, pp.
1
12
.
5.
Leskovar
,
M.
,
Cizelj
,
L.
,
Končar
,
B.
,
Parzer
,
I.
, and
Mavko
,
B.
, 2005, “
Analysis of Influence of Steam Explosion in Flooded Reactor Cavity on Cavity Structures
,” Jožef Stefan Institute, Report No. IJS-DP-9103.
6.
Cizelj
,
L.
,
Leskovar
,
M.
, and
Končar
,
B.
, 2006, “
Vulnerability of a Partially Flooded PWR Reactor Cavity to a Steam Explosion
,”
Nucl. Eng. Des.
,
236
, pp.
1617
1627
. 0029-5493
7.
Leskovar
,
M.
,
Meignen
,
R.
,
Brayer
,
C.
,
Bürger
,
M.
, and
Buck
,
M.
, 2007, “
Material Influence on Steam Explosion Efficiency: State of Understanding and Modelling Capabilities
,”
ERMSAR-2007
, Karlsruhe, Germany, pp.
1
16
.
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