The so-called in-vessel retention (IVR) was considered as a severe accident management strategy and had been certified by Nuclear Regulatory Commission (NRC) in U.S. as a standard measure for severe accident management since 1996. In the core meltdown accident, the reactor pressure vessel (RPV) integrity should be ensured during the prescribed time of 72 h. However, in traditional concept of IVR, several factors that affect the RPV failure were not considered in the structural safety assessment, including the effect of corium crust on the RPV failure. Actually, the crust strength is of significant importance in the context of a severe reactor accident in which molten core material melts through the reactor vessel and collects on the lower head (LH) of the RPV. Consequently, the RPV integrity is significantly influenced by the crust. A strong, coherent crust anchored to the RPV walls could allow the yet-molten corium to fall away from the crust as it erodes the RPV, therefore thermally decoupling the melt pool from the coolant and sharply reducing the cooling rate. Due to the thermal resistance of the crust layer, it somewhat prevents further attack of melt pool from the RPV. In the present study, the effect of crust on RPV structural behaviors was examined under multilayered crust formation conditions with consideration of detailed thermal characteristics, such as high-temperature gradient across the wall thickness. Thereafter, systematic finite element analyses and subsequent damage evaluation with varying parameters were performed on a representative RPV to figure out the possibility of high temperature induced failures with the effect of crust layer.

References

1.
Mao
,
J. F.
,
Zhu
,
J. W.
,
Bao
,
S. Y.
,
Luo
,
L. J.
, and
Gao
,
Z. L.
,
2016
, “
Creep Deformation and Damage Behavior of Reactor Pressure Vessel Under Core Meltdown Scenario
,”
Int. J. Pressure Vessels Piping
,
139–140
, pp.
107
116
.
2.
Mao
,
J. F.
,
Zhu
,
J. W.
,
Bao
,
S. Y.
,
Luo
,
L. J.
, and
Gao
,
Z. L.
,
2016
, “
Investigation on Structural Behaviors of RPV With the Effects of Critical Heat Flux and Internal Pressure
,”
ASME J. Pressure Vessel Technol.
,
139
(
2
), p.
021206
.
3.
Gaus-Liu
,
X.
,
Miassoedov
,
A.
,
Cron
,
T.
, and
Wenz
,
T.
,
2010
, “
In-Vessel Melt Pool Coolibility Test-Description and Results of LIVE Experiments
,”
Nucl. Eng. Des.
,
240
(
11
), pp.
3898
3903
.
4.
Park
,
R.-J.
,
Kang
,
K.-H.
,
Hong
,
S.-W.
, and
Kim
,
H.-Y.
,
2015
, “
Detailed Evaluation of Melt Pool Configuration in the Lower Plenum of the APR1400 Reactor Vessel During Severe Accidents
,”
Ann. Nucl. Energy
,
75
, pp.
476
482
.
5.
Mao
,
J. F.
,
Zhu
,
J. W.
,
Bao
,
S. Y.
,
Luo
,
L. J.
, and
Gao
,
Z. L.
,
2016
, “
Study on Structural Failure of RPV With Geometric Discontinuity Under Severe Accident
,”
Nucl. Eng. Des.
,
307
, pp.
354
363
.
6.
Mao
,
J. F.
,
Li
,
X. Q.
,
Bao
,
S. Y.
,
Luo
,
L. J.
, and
Gao
,
Z. L.
,
2016
, “
Investigation on Multilayer Failure Mechanism of RPV With a High Temperature Gradient From Core Meltdown Scenario
,”
Nucl. Eng. Des.
,
310
, pp.
39
47
.
7.
Government of Japan
,
2011
, “
Nuclear Emergency Response Headquarters. Report of the Japanese Government to the IAEA
,”
Ministerial Conference on Nuclear Safety-the Accident at TEPCO's Fukushima Nuclear Power Stations
, Vienna, Austria, June, pp. V1–V35.
8.
Lomperski
,
S.
, and
Farmer
,
M. T.
,
2007
, “
Experimental Evaluation of the Water Ingression Mechanism for Corium Cooling
,”
Nucl. Eng. Des.
,
237
(
9
), pp.
905
917
.
9.
Sang
,
W. N.
, and
Kune
,
Y. S.
,
2013
, “
Critical Heat Flux for APR1400 Lower Head Vessel During a Severe Accident
,”
Nucl. Eng. Des.
,
258
, pp.
116
129
.
10.
Kang
,
K. H.
,
Park
,
R. J.
,
Hong
,
S. H.
,
Hong
,
S. W.
, and
Ha
,
K. S.
,
2014
, “
An Experimental Study on Layer Inversion in the Corium Pool During Asevere Accident
,”
Nucl. Eng. Des.
,
278
, pp.
163
170
.
11.
Almyashev
,
V. I.
,
Granovsky
,
V. S.
,
Khabensky
,
V. B.
, and
Bottomley
,
P. D.
,
2016
, “
Oxidation Effects During Corium Melt in-Vessel Retention
,”
Nucl. Eng. Des.
,
305
, pp.
389
399
.
12.
Carénini
,
L.
,
Fleurot
,
J.
, and
Fichot
,
F.
,
2014
, “
Validation of ASTEC V2 Models for the Behaviour of Corium in the Vessel Lower Head
,”
Nucl. Eng. Des.
,
272
, pp.
152
162
.
13.
Wang
,
J.
,
Tian
,
W. X.
,
Feng
,
K.
,
Su
,
G. H.
, and
Qiu
,
S. Z.
,
2013
, “
Development of CHF Models for Inner and Outer RPV Gaps in Ameltdown Severe Accident
,”
Nucl. Eng. Des.
,
265
, pp.
1045
1056
.
14.
Theofanous
,
T. G.
,
Liu
,
C.
,
Additon
,
S.
,
Angelini
,
S.
,
KymaHiinen
,
O.
, and
Salmassi
,
T.
,
1997
, “
In-Vessel Coolability and Retention of a Core Melt
,”
Nucl. Eng. Des.
,
169
, pp.
1
48
.
15.
Mao, J, F., Li, X. Q., Bao, S. Y., Luo, L. J., and Gao, Z. L., 2017, “
The Influence of The Crust Layer on RPV Structural Failure Under Severe Accident Condition
,”
Nucl. Eng. Des.
,
316
, pp. 63–74.
16.
Willschutz
,
H.-G.
,
Altstadt
,
E.
,
Sehgal
,
B. R.
, and
Weiss
,
F.-P.
,
2001
, “
Coupled Thermal Structural Analysis of LWR Vessel Creep Failure Experiments
,”
Nucl. Eng. Des.
,
208
(
3
), pp.
265
282
.
17.
Willschutz
,
H.-G.
,
Altstadt
,
E.
,
Sehgal
,
B. R.
, and
Weiss
,
F.-P.
,
2006
, “
Recursively Coupled Thermal and Mechanical FEM-Analysis of Lower Plenum Creep Failure Experiments
,”
Ann. Nucl. Energy
,
33
(
2
), pp.
126
148
.
18.
Willschutz
,
H. G.
,
Altstadt
,
E.
,
Sehgal
,
B. R.
, and
Weiss
,
F. P.
,
2003
, “
Simulation of Creep Tests With French or German RPV-Steel and Investigation of a RPV-Support Against Failure
,”
Ann. Nucl. Energy
,
30
(
10
), pp.
1033
1063
.
19.
Esmaili
,
H.
, and
Khatib-Rahbar
,
M.
,
1999
, “
Analysis of in-Vessel Retention and Ex-Vessel Fuel Coolant Interaction for AP1000
,” U.S. N.R.C., Washington, DC, Report No.
NUREG/CR-6849
.https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6849/
20.
ASME Boiler and Pressure Vessel Committee on Materials, 2001, “
ASME Section II Materials—Part D: Properties
,” American Society of Mechanical Engineers, New York, pp. 796–927.
21.
Chellapandi
,
P.
, and
Alwar
,
R. S.
,
1998
, “
Development of Noniterative Self Correcting Solution (NONSS) Method for the Viscoplastic Analysis With the Chaboche Model
,”
Int. J. Numer. Methods Eng.
,
43
(
4
), pp.
621
654
.
22.
Mao, J, F., Hua, L, H., Bao, S, Y., Luo, L. J., and Gao, Z, L., 2017, ”
Investigation on the RPV Structural Behaviors Caused by Various Cooling Water Levels Under Severe Accident
,”
Eng. Fail. Anal.
,
79
, pp. 274–284.
23.
Zhang
,
L. T.
,
Zhang
,
Y. P.
, and
Qiu
,
S. Z.
,
2016
, “
COPRA Experiments on Natural Convection Heat Transfer in a Volumetrically Heated Slice Pool With High Rayleigh Numbers
,”
Ann. Nucl. Energy
,
87
, pp.
81
88
.
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