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Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments

  • Wu, Shihao (School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Zhang, Yapei (School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Wang, Dong (School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Tian, Wenxi (School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Qiu, Suizheng (School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Su, G.H. (School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
  • 투고 : 2021.06.09
  • 심사 : 2021.08.03
  • 발행 : 2022.02.25

초록

In order to meet the needs of domestic reactor severe accident analysis program, a MIDAC (Module Invessel Degraded severe accident Analysis Code) is developed and maintained by Xi'an Jiaotong University. As the accuracy of the calculation results of the analysis program is of great significance for the formulation of severe accident mitigation measures, the article select three experiments to evaluate the updated severe accident models of MIDAC. Among them, QUENCH-06 is the international standard No.45, QUENCH-16 is a test for the analysis of air oxidation, and FROMA is an out-of-pile fuel rod melting experiment recently carried out by Xi'an Jiaotong University. The heating and melting model with lumped parameter method and the steam oxidation model with Cathcart-Pawel and Volchek-Zvonarev correlations combination in MIDAC could better meet the needs of severe accident analysis. Although the influence of nitrogen still need to be further improved, the air oxidation model with NUREG still has the ability to provide guiding significance for engineering practice.

키워드

과제정보

This work was supported by the project: National Key R&D Program of China (Grant No. 2019YFB1900700).

참고문헌

  1. J.R. Wolf, D.W. Akers, L.A. Neimark, Relocation of molten material to the TMI-2 lower head, Nucl. Saf. 35 (1994) 269-279.
  2. T.S. Kress, M.W. Jankowski, J. Joosten, et al., Chernobyl accident sequence, Nucl. Saf. 28 (1987) 1-9.
  3. Y. Kim, M. Kim, W. Kim, Effect of the Fukushima nuclear disaster on global public acceptance of nuclear energy, Energy Pol. 61 (2013) 822-828. https://doi.org/10.1016/j.enpol.2013.06.107
  4. P. Hofmann, S.J. Hagen, V. Noack, et al., Chemical-physical behavior of light water reactor core components tested under severe reactor accident conditions in the CORA facility, Nucl. Technol. 118 (3) (1997) 200-224. https://doi.org/10.13182/nt118-200
  5. N.J. Kalilaine, T. Lind, J. Stuckert, et al., The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test, J. Nucl. Mater. 517 (2019) 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
  6. I.K. Madni, X.-D. Guo, MELCOR modeling of the national research universal full-length high-temperature 2 experiment. nuclear technology, Nucl. Technol. 99 (2) (1992) 203-212. https://doi.org/10.13182/NT92-A34690
  7. Z. Hozer, L. Maroti, P. Windberg, et al., Behavior of VVER fuel rods tested under severe accident conditions in the CODEX facility, Nucl. Technol. 154 (3) (2006) 302-317. https://doi.org/10.13182/nt06-a3735
  8. T. Haste, M. Steinbruck, M. Barrachin, et al., A comparison of core degradation phenomena in the CORA, QUENCH, Phebus SFD and Phebus FP experiments, Nucl. Eng. Des. 283 (2015) 129-145.
  9. M. Schwarz, G. Hache, P.V.D. Hardt, F.P. Phebus, A severe accident research programme for current and advanced light water reactors, Nucl. Eng. Des. 187 (1) (1999) 47-69. https://doi.org/10.1016/S0029-5493(98)00257-X
  10. R. Gasser, R. Gauntt, S. Bourcier, Late-phase Melt Progression Experiment: MP-2. Results and Analysis, Nuclear Regulatory Commission, Div. of Systems Technology, Washington, DC (USA), 1997, https://doi.org/10.2172/501519.NUREG/CR-6167.
  11. Y.P. Zhang, S.P. Niu, L.T. Zhang, et al., A review on analysis of LWR severe accident, J. Nucl. Eng. Radiat. Sci. 1 (4) (2015) 1-20.
  12. L. Li, Y. Zhang, W. Tian, et al., MAAP5 simulation of the PWR severe accident induced by pressurizer safety valve stuck-open accident, Prog. Nucl. Energy 77 (2014) 141-151. https://doi.org/10.1016/j.pnucene.2014.06.014
  13. L. Li, M. Wang, W. Tian, et al., in: Severe accident analysis for a typical PWR using the MELCOR code 71, 2014, pp. 30-38.
  14. P. Chatelard, N. Reinke, S. Arndt, et al., ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives, Nucl. Eng. Des. 272 (6) (2014) 119-135. https://doi.org/10.1016/j.nucengdes.2013.06.040
  15. H. Ujita, N. Satoh, M. Naitoh, et al., Development of severe accident analysis code SAMPSON in IMPACT project, J. Nucl. Sci. Technol. 36 (11) (1999) 1076-1088. https://doi.org/10.1080/18811248.1999.9726300
  16. K. Vierow, Y. Liao, J. Johnson, et al., Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes, Nucl. Eng. Des. 234 (1-3) (2004) 129-145. https://doi.org/10.1016/j.nucengdes.2004.09.001
  17. H. Austregesilo, C. Bals, K. Trambauer, Post-test calculation and uncertainty analysis of the experiment QUENCH-07 with the system code ATHLET-CD, Nucl. Eng. Des. 237 (15) (2007) 1693-1703. https://doi.org/10.1016/j.nucengdes.2007.02.019
  18. Y. Zvonarev, V. Kobzar, M. Budaev, et al., ASTEC and ICARE/CATHARE application to simulation of a VVER-1000 large break LOCA, J. Energy Eng. 4 (3) (2010) 29-36.
  19. G.H. Su, W.X. Tian, Y.P. Zhang, S.Z. Qiu, et al., Severe Accident Phenomenology of Light Water Reactors, National Defense Industry Press, 2016.
  20. P. Hofmann, S.J. Hagen, G. Schanz, et al., Reactor core materials interactions at very high temperatures, Nucl. Technol. 87 (1) (1989) 146-186.
  21. K. Mao, J. Wang, L. Li, et al., Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000, Prog. Nucl. Energy 85 (2015) 352-365. https://doi.org/10.1016/j.pnucene.2015.07.010
  22. J. Wang, W. Tian, Y. Zhang, et al., 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 (2014) 44-54. https://doi.org/10.1016/j.pnucene.2014.05.015
  23. D. Wang, Y. Zhang, R. Chen, et al., Numerical simulation of zircaloy-water reaction based on the moving particle semi-implicit method and combined analysis with the MIDAC code for the nuclear-reactor core melting process, Prog. Nucl. Energy 118 (2020).
  24. L. Sepold, W. Hering, C. Homann, Experimental and Computational Results of the QUENCH-06 Test (OECD ISP-45), Wissenschaftliche Berichte Fzka, 2004.
  25. J. Stuckert, M. Steinbruck, Experimental results of the QUENCH-16 bundle test on air ingress, Prog. Nucl. Energy 71 (2014) 134-141. https://doi.org/10.1016/j.pnucene.2013.12.001
  26. X. Shi, X. Cao, Z. Liu, Oxidation behavior analysis of cladding during severe accidents with combined codes for Qinshan Phase II Nuclear Power Plant, Ann. Nucl. Energy 58 (2013) 246-254. https://doi.org/10.1016/j.anucene.2013.03.031
  27. R.E. Pawel, J.V. Cathcart, R.A. McKee, The kinetics of oxidation of zircaloy-4 in steam at high temperatures, J. Electrochem. Soc. 126 (7) (1979) 1105-1111, 1979. https://doi.org/10.1149/1.2129227
  28. L. Baker, L.C. Just, Studies of metal-water reactions at high temperatures III, in: Experimental and Theoretical Studies of the Zirconium-Water Reaction, Argonne National Laboratory, 1962, p. 406. ANL-6548.
  29. A. Volchek, Y. Zvonarev, G. Schanz, Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations: PART II. Best-fitted parabolic correlations, Nucl. Eng. Des. 232 (1) (2004) 85-96. https://doi.org/10.1016/j.nucengdes.2004.02.014
  30. V.F. Urbanic, T.R. Heidrick, High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam, J. Nucl. Mater. 75 (2) (1978) 251-261, 1978. https://doi.org/10.1016/0022-3115(78)90006-5
  31. J.T. Prater, E.L. Courtright, Oxidation of zircaloy-4 in steam at 1300 to 2400℃. Zirconium in the Nuclear Industry, ASTM International, 1987.
  32. E. Beuzet, J.-S. Lamy, A. Bretault, et al., Modelling of Zry-4 cladding oxidation by air, under severe accident conditions using the MAAP4 code, Nucl. Eng. Des. 241 (4) (2009) 1217-1224. https://doi.org/10.1016/j.nucengdes.2010.04.024
  33. C. Bals, E. Beuzet, J. Birchley, et al., Modelling of Accelerated Cladding Degradation in Air for Severe Accident Codes, 2008.
  34. L. Fernandez-Moguel, J. Birchley, Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5, Ann. Nucl. Energy 53 (2013) 202-212. https://doi.org/10.1016/j.anucene.2012.08.030