Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment |
Gao, Pengcheng
(School of Nuclear Science and Technology, Xi'an Jiaotong University)
Zhang, Bin (School of Nuclear Science and Technology, Xi'an Jiaotong University) Li, Jishen (School of Nuclear Science and Technology, Xi'an Jiaotong University) Shan, Jianqiang (School of Nuclear Science and Technology, Xi'an Jiaotong University) |
1 | Janos Gado, Agnes Griger, Katalin Kulacsy, The fuel behaviour code FUROM and its high burn-up simulation capabilities, Nucl. Eng. Des. 327 (FEB) (2018) 274-285, https://doi.org/10.1016/j.nucengdes.2017.12.012. DOI |
2 | B. Clement, T. Haste, E. Krausmann, et al., Thematic network for a Phebus FPT1 international standard problem (THENPHEBISP), Nucl. Eng. Des. 235 (2/4) (2005) 347-357. DOI |
3 | T. Glantz, et al., DRACCAR: a multi-physics code for computational analysis of multi-rod ballooning, cool ability and fuel relocation during LOCA transients. Part Two: overview of modeling capabilities for LOCA, Nucl. Eng. Des. 339 (2018) 202-214, https://doi.org/10.1016/j.nucengdes.2018.06.022. DOI |
4 | E. Syrjalahti, T. Ikonen, V. Tulkki, Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core, Ann. Nucl. Energy 125 (2019) 121-131, https://doi.org/10.1016/j.anucene.2018.10.039. DOI |
5 | Kenneth Geelhood, Walter Luscher, J.M. Cuta, Ian Porter, FRAPTRAN-2.0: A Computer Code for the Transient Analysis of Oxide Fuel Rods, 2016. |
6 | Mazzini, Guido, Severe accident phenomenology analyses and fission gas release in advanced nuclear reactors, Pisa University Press, 2012. http://etd.adm.unipi.it/theses/available/etd-04302012-144408/. |
7 | B. Clement, T. Haste, Thematic network for a phebus FPT-1 international standard problem, in: OECD/NEA Comparison Report on International Standard Problem ISP-46, 2003. PHEBUS FPT-1). |
8 | Snl, MELCOR 2.1 Computer Code Manual - Volume 3 - Code Assessment, 2015, 2015. |
9 | L.L. Humphries. https://www.psi.ch/sites/default/files/import/emug/WS2018EN/WS_2018_03.pdf, 2018d. |
10 | Jun Ho Bae, et al., Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code, Nucl. Eng. Des. 320 (2017) 258-268, https://doi.org/10.1016/j.nucengdes.2017.05.030. DOI |
11 | P. Von der Hardt, A.V. Jones, C. Lecomte, A. Tattegrain, Nuclear Safety Research: the Phebus FP severe accident experimental program, Nucl. Saf. 35(2) (1994) 187-205. |
12 | B. Clement, R. Zeyen, The objectives of the Phebus FP experimental programme and main findings, Ann. Nucl. Energy 61 (2013) 4-10, https://doi.org/10.1016/j.anucene.2013.03.037. DOI |
13 | Irsn, Nuclear Power Reactor Core Melt Accidents - Current State of Knowledge, EDP Sciences, 2015, ISBN 978-2-7598-1835-8. |
14 | B.R. Sehgal, Nuclear safety in light water reactors severe accident phenomeneology, Academic Press Elsevier, 2012, https://doi.org/10.1016/C2010-0-67817-5. DOI |
15 | M.S. Veshchunov, V.E. Shestak, Model for melt blockage (slug) relocation and physico-chemical interactions during core degradation under severe accident conditions, Nucl. Eng. Des. 238 (1997) 3500-3507, https://doi.org/10.1016/j.nucengdes.2008.08.012, 12(2008). DOI |
16 | P. March, B. Simondi-Teisseire, Overview of the facility and experiments performed in Phebus FP, Ann. Nucl. Energy 61 (Nov) (2013) 11-22, https://doi.org/10.1016/j.anucene.2013.03.040. DOI |
17 | Xin Gong, Yijie Jiang, Shurong Ding, Yong zhong, et al., Simulation OF the IN-pile behaviors evolution IN nuclear fuel rods with the irradiation damage effects, Acta Mech. Solida Sin. 27 (2014) 567, https://doi.org/10.1016/S0894-9166(15)60001-5. DOI |
18 | K. Geelhood, W. Luscher, P. Raynaud, et al., FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup. Nuclear Regulatory Commission, Pacific Northwest Lab., Richland, WA (United States), 2015. Washington, DC (United States). Div. of Systems Technology. |
19 | T. Haste, F. Payot, P.D.W. Bottomley, Transport and deposition in the Phebus FP circuit, Ann. Nucl. Energy 61 (Nov) (2013) 102-121, https://doi.org/10.1016/j.anucene.2012.10.032. DOI |
20 | H. Kim, Sunguk Lee, Jinsu Kim, et al., Development of MERCURY for simulation of multidimensional fuel behavior for LOCA condition, Nucl. Eng. Des. 369 (2020) 110853, https://doi.org/10.1016/j.nucengdes.2020.110853. DOI |
21 | R.L. Williamson, et al., Multi-dimensional simulation of LWR fuel behavior in the BISON fuel performance code, J. Occup. Med. 68 (2016) 2930-2937, https://doi.org/10.1007/s11837-016-2115-7, 11. DOI |
22 | M. Leskovar, Simulation of the phebus FPT1 experiment with MELCOR 1.8.5, Int. Conf. Nucl. Energy New Eur. (2002) 1-8, 2002. |
23 | U.S. Nuclear Regulatory Commission, Division of Systems Analysis. Fuel Rod Behavior and Uncertainty Analysis by FRAPTRAN/TRACE/Dakota Code in Maanshan LBLOCA. Washington, DC: Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2016. |
24 | P.C. Gao, Bin Zhang, et al., DEVELOPMENT OF MECHANISTIC CLADDING RUPTURE MODEL FOR SEVERE ACCIDENT ANALYSIS AND APPLICATION, National Energy Nuclear Power Software Key Laboratory 2020 Academic Annual Meeting, 2020, pp. 499-506. |
25 | Kenneth Geelhood, Walter Luscher, Ian Porter, Material Property Correlations: Comparisons between FRAPCON-4.0, FRAPTRAN-2.0, and MATPRO, 2015, https://doi.org/10.2172/1030897. DOI |
26 | Institut de Protection et de Surete Nucleaire (Ipsn), Final Report FPT1, PHEBUSPF, IPSN/JRC, Saint Paul-lez-Durance Cedex, France, 2000. |
27 | T. Ikeda, M. Terada, H. Karasawa, et al., Analysis of core degradation and fission products release in phebus FPT1 test at IRSN by detailed severe accidents analysis code, IMPACT/SAMPSON, J. Nucl. Sci. Technol. 40 (8) (2003) 591-603, https://doi.org/10.1080/18811248.2003.9715396. DOI |
28 | Snl, MELCOR 2.2 Computer Code Manual - Volume 1 - User Guide, 2017, 2017. |
29 | U.S. Nrc, Accident Source Terms for Light-Water Nuclear Power Plants, 1995. NUREG-1465. |
30 | Snl, MELCOR Best Practices as Applied in the State-Of-The-Art Reactor Consequence Analyses (SOARCA) Project, U.S. NC Report NUREG/CR-7008, 2014, 2014. |
31 | S. Suman, Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations, Nuclear Engineering and Technology (2021), https://doi.org/10.1016/j.net.2020.07.017. DOI |
32 | Georges Repetto, et al., Preliminary analyses of the phebus FPT3 experiment using severe accident codes (ATHLET-CD, ICARE/CATHARE, MELCOR), Nucl. Technol. 176 (2011) 352-371, https://doi.org/10.13182/NT11-A13313, 3. DOI |
33 | A.G. Pastore, et al., Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: cladding modeling developments and simulation of separate-effects experiments, J. Nucl. Mater. 543 (2020), https://doi.org/10.1016/j.jnucmat.2020.152537. DOI |
34 | Pengcheng Gao, Bin Zhang, et al., Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I: module verification and application in CAP1400, Ann. Nucl. Energy 158 (2021) 2-3, https://doi.org/10.1016/j.anucene.2021.108305, 108305. DOI |
35 | R.O. Gauntt, J.E. Cash, R.K. Cole, et al., MELCOR Computer Code Manuals 1-2, version 1.8.6, U.S. Nuclear Regulatory Commission, Sandia National Laboratories, 2005. |
36 | MELCOR Computer Code Manuals Vol. 3: MELCOR Assessment Problems Version 2.1.7347, 2015. |
37 | Timo Ikonen, et al., Module for thermomechanical modeling of LWR fuel in multiphysics simulations, Ann. Nucl. Energy 84 (oct) (2015) 111-121, https://doi.org/10.1016/j.anucene.2014.11.004. DOI |