Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code

  • Khvostov, G. (Paul Scherrer Institut (PSI))
  • Received : 2020.02.28
  • Accepted : 2020.05.14
  • Published : 2020.12.25
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Abstract

Cladding failure in a fuel rod during operation in a BWR is analyzed using a FALCON code-based model. Comparative calculation with a neighbouring, intact rod is presented, as well. A considerable 'hot spot' effect in cladding temperature is predicted with the SLICE-DO model due to a thermal barrier caused by the localized crud deposition. Particularly significant overheating is expected to occur on the affected side of the cladding of the failed rod, in agreement with signs of significant localized crud deposition as revealed by Post Irradiation Examination. Different possibilities (criteria) are checked, and Pellet-Cladding Mechanical Interaction (PCMI) is shown to be one of the plausible potential threats. It is shown that PCMI could lead to discernible concentrated inelastic deformation in the overheated part of the cladding. None of the specific mechanisms considered can be experimentally or analytically identified as an only cause of the rod failure. However, according to the current calculation, a possibility of cladding failure by PCMI cannot be excluded if the crud thickness exceeded 300 ㎛.

Keywords

Acknowledgement

The activity on fuel behaviour analysis methods development at Paul Scherrer Institute (PSI) has been partly funded by Swiss Federal Nuclear Safety Inspectorate (ENSI) in the framework of the STARS program. Some specific studies have been supported by swissnuclear through its Expert Group on Fuel Safety (ESB). The boundary conditions for fuel behaviour analysis, as provided by Dr. K. Nikitin and Mr. H. Ferroukhi of PSI based on their TRACE and SIMULATE-3 code calculations are acknowledged with thanks. The experimental data of Post-Irradiation Examination carried out by Dr. D. Gavillet, Dr. H. Wiese and Dr. M. Martin of Paul Scherrer Institute was particularly important for the present modelling work. The author would like to express his deepest gratitude to Dr. A. Gorzel from Swiss Federal Nuclear Safety Inspectorate, for his review of the manuscript.

References

  1. I. Clifford, M. Pecchia, R. Mukin, C. Cozzo, H. Ferroukhi, A. Gorzel, Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs, Ann. Nucl. Energy 130 (2019) 440-451, https://doi.org/10.1016/j.anucene.2019.03.017.
  2. G. Khvostov, Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code, Nucl. Eng. Technol. 52 (2020) 135-147, https://doi.org/10.1016/j.net.2019.07.010.
  3. Epri Licence Agreement, Agreement No. 03-0601 VP, 30.09.2004.
  4. Epri Product Id 1011307, Fuel analysis and licensing Code: FALCON MOD01, in: Theoretical and Numerical Bases, vol. 1, EPRI, 2004 web, https://www.epri.com/#/pages/product/000000000001011307/.
  5. Epri Product Id 1011309, Fuel analysis and licensing code: FALCON MOD01, in: Verification and Validation, vol. 3, EPRI, 2004 web, https://nam03.safelinks.protection.outlook.com/?url=https%3A%2F%2Fwww.epri.com%2F%23%2Fpages%2Fproduct%2F000000000001011309%2F&data=02%7C01%7CA.Somasundaram%40elsevier.com%7Cdfb705d26c36454483d908d7ff170788%7C9274ee3f94254109a27f9fb15c10675d%7C0%7C0%7C637258346701888203&sdata=tDiUK9I%2FPvsEPlSQATkxnI8nTkblBp7PONqRygFul%2FA%3D&reserved=0.
  6. G. Khvostov, K. Mikityuk, M.A. Zimmermann, A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code, Nucl. Eng. Des. 241 (2011) 2983-3007, https://doi.org/10.1016/j.nucengdes.2011.06.020.
  7. M. Limback, T. Andersson, A model for analysis of the effects of final annealing on the in- and out-of-reactor creep behaviour of zircaloy cladding, in: E.R. Bradley, G.P. Sabol (Eds.), ASTM STP 1295, American Society for Testing and Materials, 1996, pp. 448-468, https://doi.org/10.1520/STP16185S.
  8. Matpro - Version 11, A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior. NUREG/CR-0497 TREE1280, February 1979.
  9. M. Pecchia, H. Ferroukhi, A. Vasiliev, P. Grimm, Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle checkup methodology, Ann. Nucl. Energy 129 (2019) 67-78, https://doi.org/10.1016/j.anucene.2019.01.047.
  10. United States Nuclear Regulatory Commission, TRACE v5.840 Theory Manual, Division of Safety Analysis, U.S. NRC, 2013.
  11. N. Cinosi, I. Haq, M. Bluck, S.P. Walker, The effective thermal conductivity of crud and heat transfer from crud-coated PWR fuel, Nucl. Eng. Des. 241 (2011) 792-798, https://doi.org/10.1016/j.nucengdes.2010.12.015.
  12. S.L. Hayes, K.L. Peddicord, Radiative heat transfer in porous uranium dioxide, J. Nucl. Mater. 202 (1993) 87-97, https://doi.org/10.1016/0022-3115(93)90032-T.
  13. G. Khvostov, V. Novikov, A. Medvedev, S. Bogatyr, Approaches to modeling of high burn-up structure and analysis of its effects on the behaviour of light water reactor fuels in the START-3 fuel performance code, in: Proc.: 2005 LWR Fuel Performance Meeting, 2005, Paper No. 1104, 2005.
  14. Epri Product Id 1011308, Fuel analysis and licensing code: FALCON MOD01, in: User's Manual, vol. 2, EPRI, 2004. Web, https://www.epri.com/#/pages/product/000000000001011308/.
  15. A. Kucuk, Bo Cheng, G.A. Potts, B. Shiralkar, D. Morgan, G. Gose, K. Epperson, Crud deposition modeling on BWR fuel rods, proc., in: 2014 Water Reactor Fuel Performance Meeting, Top Fuel, LWR Fuel Performance Meeting, Paper No. 100029, 2014.
  16. G. Khvostov, W. Lyon, M. Zimmermann, Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface, Ann. Nucl. Energy 62 (2013) 398-412, https://doi.org/10.1016/j.anucene.2013.07.002.
  17. Review of Fuel Failures in Water Cooled Reactors, IAEA Nuclear Energy Series, 2010. No. NF-T-2.1.
  18. US Nuclear Regulatory Commission Standard Review Plan 4.2 - Fuel System Design, (USNRC SRP 4.2), 2007, NUREG-0800 Rev. 3, U.S. NRC, 2007 web, https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/ch4/.
  19. F. Ribeiro, G. Khvostov, Multi-scale approach to advanced fuel modelling for enhanced safety, Prog. Nucl. Energy 84 (2015) 24-35, https://doi.org/10.1016/j.pnucene.2015.03.022.
  20. W. Lyon, R. Montgomery, J. Rashid, S. Yagnik, PCI analysis and fuel rod failure prediction using FALCON, Proc. Top Fuel (2009). Paper No. 2125.
  21. A. Kucuk, R. Nelson, A. Avila, K. Szwarc, K. Epperson, G.A. Potts, J. Giannelli, G. Gose, BWR water chemistry transients and crud-Induced corrosion fuel failure risk assessment, in: Proc. Top Fuel, 2019, p. 1208, 2019.