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COMPARISON OF DIFFUSION COEFFICIENTS AND ACTIVATION ENERGIES FOR AG DIFFUSION IN SILICON CARBIDE

  • KIM, BONG GOO (Advanced Nuclear Fuel Development Division, Korea Atomic Energy Research Institute) ;
  • YEO, SUNGHWAN (Advanced Nuclear Fuel Development Division, Korea Atomic Energy Research Institute) ;
  • LEE, YOUNG WOO (Advanced Nuclear Fuel Development Division, Korea Atomic Energy Research Institute) ;
  • CHO, MOON SUNG (Advanced Nuclear Fuel Development Division, Korea Atomic Energy Research Institute)
  • Received : 2014.12.15
  • Accepted : 2015.05.08
  • Published : 2015.10.25

Abstract

The migration of silver (Ag) in silicon carbide (SiC) and $^{110m}Ag$ through SiC of irradiated tristructural isotropic (TRISO) fuel has been studied for the past three to four decades. However, there is no satisfactory explanation for the transport mechanism of Ag in SiC. In this work, the diffusion coefficients of Ag measured and/or estimated in previous studies were reviewed, and then pre-exponential factors and activation energies from the previous experiments were evaluated using Arrhenius equation. The activation energy is $247.4kJ{\cdot}mol^{-1}$ from Ag paste experiments between two SiC layers produced using fluidized-bed chemical vapor deposition (FBCVD), $125.3kJ{\cdot}mol^{-1}$ from integral release experiments (annealing of irradiated TRISO fuel), $121.8kJ{\cdot}mol^{-1}$ from fractional Ag release during irradiation of TRISO fuel in high flux reactor (HFR), and $274.8kJ{\cdot}mol^{-1}$ from Ag ion implantation experiments, respectively. The activation energy from ion implantation experiments is greater than that from Ag paste, fractional release and integral release, and the activation energy from Ag paste experiments is approximately two times greater than that from integral release experiments and fractional Ag release during the irradiation of TRISO fuel in HFR. The pre-exponential factors are also very different depending on the experimental methods and estimation. From a comparison of the pre-exponential factors and activation energies, it can be analogized that the diffusion mechanism of Ag using ion implantation experiment is different from other experiments, such as a Ag paste experiment, integral release experiments, and heating experiments after irradiating TRISO fuel in HFR. However, the results of this work do not support the long held assumption that Ag release from FBCVD-SiC, used for the coating layer in TRISO fuel, is dominated by grain boundary diffusion. In order to understand in detail the transport mechanism of Ag through the coating layer, FBCVD-SiC in TRISO fuel, a microstructural change caused by neutron irradiation during operation has to be fully considered.

Keywords

Acknowledgement

Supported by : National Research Foundation of Korea (NRF)

References

  1. R.N. Morris, D.P. Petti, D.A. Powers, B.E. Boyack, M.B. Rubin, TRISO-Coated Particle Fuel Phenomenon Identification and Ranking Tables (PIRTs) for Fission Product Transport due to Manufacturing Operations, and Accidents, NUREG/CR-6844, U.S. Nuclear Regulatory Commission, Washington, DC, 2004 (20555-0001).
  2. IAEA, Fuel Performance and Fission Product Behavior in Gas Cooled Reactors, IAEA-TECDOC-978, International Atomic Energy Agency, Vienna, Austria, 1997.
  3. H.J. MacLean, R.G. Ballinger, L.E. Kolaya, S.A. Simonson, N. Lewis, M.E. Hanson, The effect of annealing at $1500^{\circ}C$ on migration and release of ion implanted silver in CVD silicon carbide, J. Nucl. Mater. 357 (2006) 31-47. https://doi.org/10.1016/j.jnucmat.2006.05.043
  4. D. Olander, Nuclear fuels e Present and future, J. Nucl. Mater. 389 (2009) 1-22. https://doi.org/10.1016/j.jnucmat.2009.01.297
  5. L.L. Snead, T. Nozawa, Y. Katoh, T.-S. Byun, S. Kondo, D.A. Petti, Handbook of SiC properties for fuel performance modeling, J. Nucl. Mater. 371 (2007) 329-377. https://doi.org/10.1016/j.jnucmat.2007.05.016
  6. B.G. Kim, S.J. Park, S.T. Hong, B.C. Lee, K.-C. Jeong, Y.-K. Kim, W.K. Kim, Y.W. Lee, M.S. Cho, Y.W. Kim, Irradiation device for irradiation testing of coated particle fuel at HANARO, Nucl. Eng. Tech. 45 (2013) 941-950. https://doi.org/10.5516/NET.07.2013.045
  7. T. Besmann, Thermochemical Behaviour of Oxide Nuclear Fuel to High Burn-up: Effect of Lanthanides, Presentation at MS&T, Columbus, Ohio, 2011.
  8. W.E. Lee, M. Gilbert, S.T. Murphy, R.W. Grimes, Opportunities for advanced ceramics and composites in the nuclear sector, J. Am. Ceram. Soc. 96 (2013) 2005-2030. https://doi.org/10.1111/jace.12406
  9. M. Barrachin, R. Dubourg, S. de Groot, M.P. Kissanea, K. Bakker, Fission-product behavior in irradiated TRISO-coated particles: results of the HFR-EU1bis experiment and their interpretation, J. Nucl. Mater. 415 (2011) 104-116. https://doi.org/10.1016/j.jnucmat.2011.05.047
  10. O. Seeger, K. Knebel, W. de Weerd, P. Carbol, P.D.W. Bottomley, V.V. Rondinella, H.-J. Allelein, Simulated accident testing of a fuel element from the HFR-EU1bis irradiation campaign, Nucl. Eng. Des. 271 (2014) 171-179. https://doi.org/10.1016/j.nucengdes.2013.11.028
  11. I.J. van Rooyen, T.M. Lillo, Y.Q. Wu, Identification of silver and palladium in irradiated TRISO coated particles of the AGR-1 experiment, J. Nucl. Mater. 446 (2014), 187-186. https://doi.org/10.1016/j.jnucmat.2013.11.041
  12. H. Nabielek, P.E. Brown, P. Offerman, Silver release from coated particle fuel, Nucl. Tech. 35 (1977) 483-493. https://doi.org/10.13182/NT35-483
  13. H.J. MacLean, Silver Transport in CVD SiC, PhD Thesis, Massachusetts Institute of Technology, 2004.
  14. E. Friedland, J.B. Malherbe, N.G. van der Gerg, T. Hlatshwayo, A.J. Botha, E. Wendler, W. Wesch, Study of silver diffusion in silicon carbide, J. Nucl. Mater. 389 (2009) 326-331. https://doi.org/10.1016/j.jnucmat.2009.02.022
  15. T.T. Hatshwayo, Diffusion of Silver in 6H-SiC, PhD Thesis, University of Pretoria, 2010.
  16. K.Verfondern, R.C.Martin, R.Moormann, Methodsand Data for HTGR Fuel Performance and Radionuclide Release Modeling during Normal Operation and Accidents for Safety Analyses, Jul-2721, Forschungszentrum Julich GmbH, January 1993.
  17. W. Amian, D. Stover, Diffusion of silver and cesium in siliconcarbide coatings of fuel particles for high temperature gascooled reactors, Nuc. Tech. 61 (1983) 475-486. https://doi.org/10.13182/NT61-475
  18. I. Szlufarska, D.D. Morgan, S. Khalil, D. Shrader, A. Heim, Modeling of Ag diffusion in TRISO coated fuel particles, in: Embedded Topical on Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors. ANS Annual Meeting, San Diego, CA, USA, June 13-17, 2010.
  19. J.J. van der Merwe, Evaluation of silver transport through SiC during the German HTR fuel program, J. Nucl. Mater. 395 (2009) 99-111. https://doi.org/10.1016/j.jnucmat.2009.09.024
  20. E. Lopez-Honorato, D.X. Yang, J. Tan, P.J. Meadows, P. Xiao, Silver diffusion in coated fuel particles, J. Am. Ceram. Soc. 93 (2010) 3076-3079. https://doi.org/10.1111/j.1551-2916.2010.04055.x
  21. E. Lopez-Honorato, H. Zhang, D.X. Yang, P. Xiao, Silver diffusion in silicon carbide coatings, J. Am. Ceram. Soc. 94 (2011) 3064-3071. https://doi.org/10.1111/j.1551-2916.2011.04544.x
  22. T.J. Gerczak, T.R. Allen, Z. Zhu, Fission product transport of cesium and silver in CVD-SiC, in: Embedded Topical on Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors. ANS Annual Meeting San Diego, CA, USA, June 13-17, 2010.
  23. T.J. Gerczak, Understanding Ag Release from TRISO Fuel through Surrogate Diffusion Experiments and Fuel Analysis, PhD Thesis, University of Wisconsin-Madison, 2013.
  24. D. Shrader, S.M. Khalil, T. Gerczak, T.R. Allen, A.J. Heim, I. Szlufarska, D. Morgan, Ag diffusion in cubic silicon carbide, J. Nucl. Mater. 408 (2011) 257-271. https://doi.org/10.1016/j.jnucmat.2010.10.088
  25. X. Geng, F. Yang, N. Rohbeck, P. Xiao, An original way to investigate silver migration through silicon carbide coating in TRISO particles, J. Am. Ceram. Soc. 97 (2014) 1979-1986. https://doi.org/10.1111/jace.12872
  26. H. Nabielek, SiC for fuel, in: 33rd ICACCS Discussion Group of Symposium 10 on Silicon Carbide, Daytona Beach, FL, 2009.
  27. J.J. van der Merwe, Modelling Silver Transport in Spherical HTR Fuel, Ph.D. Thesis, UP, 2009.
  28. E. Lopez-Honorato, J. Tan, P.J. Meadows, G. Marsh, P. Xiao, TRISO coated fuel particles with enhanced SiC properties, J. Nucl. Mater. 392 (2009) 219-224. https://doi.org/10.1016/j.jnucmat.2009.03.013
  29. S. Khalil, N. Swaminathan, D. Shrader, A.J. Heim, D.D. Morgan, I. Szlufarska, Diffusion of Ag along ${\Sigma}3$ grain boundaries in 3C-SiC, Phys. Rev. B 84 (2011) 214104. https://doi.org/10.1103/PhysRevB.84.214104
  30. L.Tan, T.R. Allen, J.D.Hunn, J.H. Miller, EBSD for microstructureand property characterization of the SiC-coating in TRISO fuel particles, J. Nucl. Mater. 372 (2008) 400-404. https://doi.org/10.1016/j.jnucmat.2007.04.048
  31. T. Fujita, Z. Horita, T.G. Langdon, Using grain Boundary engineering to evaluate the diffusion characteristics in ultrafine-grained Al-Mg and Al-Zn alloys, Mater. Sci. Eng. A371 (2004) 241-250. https://doi.org/10.1016/j.msea.2003.12.042
  32. Y. Chen, A. Schuh, Geometric considerations for diffusion in polycrystalline solids, J. Appl. Phys. 101 (2007), 063524-1. https://doi.org/10.1063/1.2711820
  33. J.H. O'Connell, J.H. Neethling, Ag transport in high temperature neutron irradiated 3C-SiC, J. Nucl. Mater. 445 (2014) 20-25. https://doi.org/10.1016/j.jnucmat.2013.10.050
  34. E.J. Olivier, J.H. Neethling, The role of Pd in the transport of Ag in SiC, J. Nucl. Mater. 432 (2013) 252-260. https://doi.org/10.1016/j.jnucmat.2012.07.033
  35. J.H. Neethling, J.H. O'Connell, E.J. Olivier, Palladium assisted silver transport in polycrystalline SiC, Nucl. Eng. Des. 25(2012) 230-234.
  36. H. Nabielek, D. Goodin, W. Scheffel, Criteria for a high performance particle, in: HTR-TH International HTR Fuel Seminar. Brussels, Belgium, 2001.
  37. R.L. Pearson, R.J. Lauf, T.B. Lindemer, The Interaction of Palladium, the Rare Earths and Silver with Silicon Carbide in HTGR Fuel Particles, ORNL/TM-8059, Oak Ridge National Laboratory, 1982.
  38. Y. Katoh, N. Hashimoto, S. Kondo, L.L. Snead, A. Kohyama, Microstructural development in cubic silicon carbide during irradiation at elevated temperatures, J. Nucl. Mater. 351(2009) 228-240.
  39. G.M. de Bellefon, B.D. Wirth, Kinetic Monte Carlo (KMC) simulation of fission product silver transport through TRISO fuel particle, J. Nucl. Mater. 413 (2011) 122-131. https://doi.org/10.1016/j.jnucmat.2011.04.010

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