The occurrence of Fukushima has increased the focus on the development of severe accident codes and their applications. As a part of Chinese “National Major Projects,” a module in-vessel degraded analysis code (MIDAC) is currently being developed at Xi’an Jiaotong University. The developing situation of a candling module and relevant calculation for CPR1000 for large break loss of coolant analysis (LOCA) are presented in this paper. The candling module focuses on the melting, moving, and relocation of the melting core materials and necessary thermal hydraulic information. MIDAC’s LOCA accident calculation results of Chinese pressure reactor 1000 (CPR1000) cover the melting mass distribution, peak temperature, and hydrogen generation. The results have been compared with MAAP. Through comparison, the candling module of MIDAC proved to be able to predict the moving trend of the molten material mass relocation in the reactor pressure vessel.
Issue Section:
Research Papers
References
1.
Sehgal
, B. R.
, 2012
, “Light Water Reactor Safety: A Historical Review (Chap. 1),” Nuclear Safety in Light Water Reactors
, S.
Bal Raj
, , ed., Academic Press
, Boston
, pp. 1
–88
.2.
Muller
, W. C.
, 2006
, “Review of Debris Bed Cooling in the TMI-2 Accident
,” Nucl. Eng. Des.
, 236
(19–21
), pp. 1965
–1975
.3.
Sehgal
, B. R.
, 2001
, “Accomplishments and Challenges of the Severe Accident Research
,” Nucl. Eng. Des.
, 210
(1
), pp. 79
–94
. 0029-549310.1016/S0029-5493(01)00433-24.
Ramana
, M. V.
, and Saikawa
, E.
, 2011
, “Choosing a Standard Reactor: International Competition and Domestic Politics in Chinese Nuclear Policy
,” Energy
, 36
(12
), pp. 6779
–6789
. 0149-938610.1016/j.energy.2011.10.0225.
Thomas
, S.
, 2012
, “What Would the Fukushima Disaster Change?
,” Energy Policy
, 45
, pp. 12
–17
. 0301-421510.1016/j.enpol.2012.02.0106.
Bolshov
, L.
, Strizhov
, V.
, and Kisselev
, A.
, 1997
, “Severe Accident Codes Status and Future Development
,” Nucl. Eng. Des.
, 173
, pp. 247
–256
. 0029-549310.1016/S0029-5493(97)00114-37.
Rubin
, A.
, Basu
, S.
, Notafrancesco
, A.
, and Allison
, C.
, 1996
, “USNRC Severe Accident Codes- Process, Status and Future Direction of Modeling and Supporting Experimental Activities
,” Heat and Mass Transfer in Severe Nuclear Reactor Accidents
, International Centre for Heat and Mass Transfer, Bagel House
, New York
, pp. 447
–461
.8.
Lee
, M.
, and Lee
, G. D.
, 1992
, “Quantification of Severe Accident Source Terms of BWR4 Reactor With Mark I Containment Using Source Term Code Package
,” Nucl. Eng. Des.
, 138
(3
), pp. 313
–337
. 0029-549310.1016/0029-5493(92)90069-89.
Lee
, M.
, and Ko
, Y. C.
, 2008
, “Quantification of Severe Accident Source Term of a Westinghouse 3-Loop Plant
,” Nucl. Eng. Des.
, 238
(4
), pp. 1080
–1092
. 0029-549310.1016/j.nucengdes.2007.09.00310.
Merrill
, B. J.
, Humrickhouse
, P. W.
, and Moore
, R. L.
, 2010
, “A Recent Version of MELCOR for Fusion Safety Applications
,” Fusion Eng. Des.
, 85
(7–9
), pp. 1479
–1483
.11.
Ferng
, Y. M.
, Liu
, Y. T.
, and Shih
, C.
, 2010
, “Investigating the Execution of EOPs in LOTDFP+ATWS+LOCA Scenarios for an ABWR Using MAAP Code
,” Nucl. Eng. Des.
, 240
(1
), pp. 198
–203
.12.
Layly
, V. D.
, Spitz
, P.
, Tirini
, S.
, and Mailliat
, A.
, 1996
, “Analysis of the Phebus FPTO Containment Thermal Hydraulics With the Jiricho and Trio-VF Codes
,” Nucl. Eng. Des.
, 166
(3
), pp. 413
–426
. 0029-549310.1016/S0029-5493(96)01258-713.
Sharma
, B. M.
, Tiwari
, A.
, Srivastava
, A.
, Kumar
, R.
, Lele
, H. G.
, Khanna
, A.
, Mushi
, P.
, 2011
, “Analysis of PHWR LP Turbine Steady State Using RELAP/ SCDAP Code
,” Energy Procedia
, 7
, pp. 367
–373
. 1876-610210.1016/j.egypro.2011.06.04814.
Carroll
, D. E.
, Tills
, J. L.
, Valdez
, G. D.
, Bergeron
, K. D.
, and Williams
, D. C.
, 1987
, “Integrated Analysis of Core Debris Interactions and Their Effects on Containment Integrity Using the Contain Computer Code
,” Nucl. Eng. Des.
, 104
(3
), pp. 277
–283
. 0029-549310.1016/0029-5493(87)90205-615.
Makynen
, J. M.
, Jokiniemi
, J. K.
, and Kauppinen
, E. I.
, 1997
, “LWR Aerosol Experiments at Victoria Module Containment
,” J. Aerosol Sci.
, 28
(1
), pp. s715
–s716
. 0021-850210.1016/S0021-8502(97)85356-616.
Bandini
, G.
, Meloni
, P.
, Polidori
, M.
, and Lombardo
, C.
, 2011
, “Validation of CATHARE V2.5 Thermal-Hydraulic Code Against Full-Scale PERSEO Tests for Decay Heat Removal in LWRs
,” Nucl. Eng. Des.
, 241
(12
), pp. 4662
–4671
. 0029-549310.1016/j.nucengdes.2011.02.03417.
Bolshov
, L.
, Strizhov
, V.
, and Kisselev
, A.
, 1997
, “Severe Accident Codes Status and Future Development
,” Nucl. Eng. Des.
, 173
, pp. 247
–256
. 0029-549310.1016/S0029-5493(97)00114-318.
Wang
, J.
, Tian
, W. X.
, Lu
, J. N.
, Ma
, Y. Y.
, Su
, G. H.
, and Qiu
, S. Z.
, 2013
, “The Research on Core Molten Materials Process: Oxidation
,” 21st International Conference of Nuclear Engineering
, Chengdu, China
, July 21–Aug. 2
, ASME
, New York
.19.
Wang
, J
, Tian
, W. X.
, Fan
, Y. Q.
, Mao
, K. Y.
, Lu
, J. N.
, Su
, G. H.
, and Qiu
, S. Z.
, 2014
, “The Development of a Zirconium Oxidation Calculating Program Module for Module In-vessel Degraded Analysis Code MIDAC
,” Prog. Nucl. Energy
, 73
, pp. 162
–171
. 0149-197010.1016/j.pnucene.2014.02.00620.
Sugiyama
, K. I.
, Aoki
, H.
, Su
, G. H.
, and Kojima
, Y.
, 2005
, “Experimental Study on Coolability of Particulate Core-Metal Debris Bed with Oxidation, (I) Fragmentation and Enhanced Heat Transfer in Zircaloy-50 wt% Ag Debris Bed
,” J. Nucl. Sci. Technol.
, 42
(12
), pp. 1081
–1084
. 0022-313110.1080/18811248.2005.971106121.
Su
, G. H.
, Sugiyama
, K. I.
, Aoki
, H.
, and Kimura
, I.
, 2006
, “Experiment Study on Coolability of Particulate Core-Metal Debris Bed With Oxidization, (II) Fragmentation and Enhanced Heat Transfer in Zircaloy Debris Bed
,” J. Nucl. Sci. Technol.
, 43
(5
), pp. 537
–545
. 0022-313110.1080/18811248.2006.971113222.
Yu
, H. X.
, Zhang
, Y. P.
, Su
, G. H.
, Qiu
, S. Z.
, and Tian
, W. X.
, 2012
, “A Theoretical CHF Module for Downward Facing Surfaces and Gaps Under Saturated Boiling
,” Int. J. Multiphase Flow
, 45
, pp. 30
–39
. 0301-932210.1016/j.ijmultiphaseflow.2012.05.00123.
Wang
, J.
, Tian
, W. X.
, Feng
, K.
, Yu
, H. X.
, Zhang
, Y. P.
, Su
, G. H.
, and Qiu
, S. Z.
, 2013
, “Development of CHF Models for Inner and Outer RPV Gaps in a Meltdown Severe Accident
,” Nucl. Eng. Des.
, 265
, pp. 1045
–1056
. 0029-549310.1016/j.nucengdes.2013.07.03524.
Chen
, R. H.
, Corradini
, M.
, Su
, G. H.
, and Qiu
, S. Z.
, 2012
, “Development of a Solidification Module for TEXASVI and Application to FARO L14 Analysis
,” Nucl. Sci. Eng.
, 249
, pp. 1
–10
. 0029-563910.1016/j.nucengdes.2012.03.03425.
Wang
, J.
, Tian
, W. X.
, Zhang
, Y. P.
, Chen
, L.
, Li
, L. Z.
, Zhang
, L. T.
, Zhou
, Y. K.
, Su
, G. H.
, Qiu
, S. Z.
, 2014
, “The Development of Module In-Vessel Degraded Severe Accident Analysis Code MIDAC and the Relevant Research for CPR1000 During the Station Blackout Scenario
,” Prog. Nucl. Energy
, 76
, pp. 44
–54
. 0149-197010.1016/j.pnucene.2014.05.01526.
Chien
, C. S.
, Wang
, S. J.
, and Chiang
, S. C.
, 2008
, “Development of Parameter-Identification Capability for MAAP4 Code
,” Nucl. Technol.
, 161
(3
), pp. 203
–209
.27.
Deng
, J.
, and Cao
, X. W.
, 2008
, “Preliminary Analysis of Hydrogen Distribution and Risk Under Severe Accident Conditions for QINSHANNPP Unit 2 Containment
,” Nucl. Power Eng.
, 29
(2
), pp. 78
–84
.28.
Pu
, J. L.
, 2008
, “The Formation of the Improved Chinese Pressurized Water Reactor Technology—CPRl000
,” Eng. Sci.
, 10
(3
), pp. 54
–57
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