Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

MULTISCALE MODELLING FOR THE FISSION GAS BEHAVIOUR IN THE TRANSURANUS CODE

  • Van Uffelen, P. (European Commission, Joint Research Centre, Institute for Transuranium Elements) ;
  • Pastore, G. (Politecnico di Milano, Department of Energy, Nuclear Engineering Division (CeSNEF)) ;
  • Di Marcello, V. (European Commission, Joint Research Centre, Institute for Transuranium Elements) ;
  • Luzzi, L. (Politecnico di Milano, Department of Energy, Nuclear Engineering Division (CeSNEF))
  • Received : 2011.11.19
  • Published : 2011.12.25
Download PDF
⟨ Previous Next ⟩

Abstract

A formulation is proposed for modelling the process of intra-granular diffusion of fission gas during irradiation of $UO_2$ under both normal operating conditions and power transients. The concept represents a simple extension of the formulation of Speight, including an estimation of the contribution of bubble motion to fission gas diffusion. The resulting equation is formally identical to the diffusion equation adopted in most models that are based on the formulation of Speight, therefore retaining the advantages in terms of simplicity of the mathematical-numerical treatment and allowing application in integral fuel performance codes. The development of the new model proposed here relies on results obtained by means of molecular dynamics simulations as well as finite element computations. The formulation is proposed for incorporation in the TRANSURANUS fuel performance code.

Keywords

References

  1. Watanabe, T., et al., Thermal Transport in Off-Stoichiometric Uranium Dioxide by Atomic Level Simulation. J. Am. Ceram. Soc., 2009. 92(4): p. 850-856. https://doi.org/10.1111/j.1551-2916.2009.02966.x
  2. Parfitt, D.C. and R.W. Grimes, Predicting the probability for fission gas resolution into uranium dioxide. Journal of Nuclear Materials. In Press, Corrected Proof.
  3. Middleburgh, S.C., et al., Swelling due to fission products and additives contained within the uranium dioxide lattice. Journal of Nuclear Materials, 2011. submitted for publication.
  4. Kotomin, E.A., et al., Implementing first principles calculations of defect migration in a fuel performance code for UN simulations. Journal of Nuclear Materials, 2009. 393: p. 292-299. https://doi.org/10.1016/j.jnucmat.2009.06.016
  5. White, R.J. and M.O. Tucker, A new fission gas release model. Journal of Nuclear Materials, 1983. 118: p. 1-38. https://doi.org/10.1016/0022-3115(83)90176-9
  6. Matzke, H., Gas release mechanisms in $UO_{2}$ - a critical overview. Radiation Effects, 1980. 53: p. 219-242. https://doi.org/10.1080/00337578008207118
  7. White, R.J. and M.O. Tucker. A new mechanistic model for the calculation of fission gas release. in International Topical Meeting on LWR Fuel Performance. 1994. West Palm Beach, Florida.
  8. Lassmann, K. and H. Benk, Numerical algorithms for intragranular fission gas release. Journal of Nuclear Materials, 2000. 280(2): p. 127-135. https://doi.org/10.1016/S0022-3115(00)00044-1
  9. Lassmann, K., et al., TRANSURANUS Handbook. 2005.
  10. Speight, M.V., A calculation on the migration of fission gas in material exhibiting precipitation and re-solution of gas atoms under irradiation. Nuclear Science and Engineering, 1969. 37: p. 180-185. https://doi.org/10.13182/NSE69-A20676
  11. Losonen, P., On the behaviour of intragranular fission gas in $UO_{2}$ fuel. Journal of Nuclear Materials, 2000. 280: p. 56-72. https://doi.org/10.1016/S0022-3115(00)00028-3
  12. Veshchunov, M.S., On the theory of fission gas bubble evolution in irradiated $UO_{2}$. Journal of Nuclear Materials 2000. 277 p. 67-81. https://doi.org/10.1016/S0022-3115(99)00136-1
  13. Hoppe, N., et al., COMETHE version 4D release 021 (4.4- 021), Vol. 1, General Description. April 1995, Belgonucleaire Report BN-9409844/220 A.
  14. Koo, Y.H., B.H. Lee, and D.S. Sohn, COSMOS: A computer code to analyze LWR UO2 and MOX fuel to high burn-up. Annals of Nuclear Energy, 1999. 26: p. 47-67. https://doi.org/10.1016/S0306-4549(98)00033-4
  15. Koo, Y.H., B.H. Lee, and D.S. Sohn, Analysis of fission gas release and gaseous swelling in $UO_{2}$ fuel under the effect of external restraint. Journal of Nuclear Materials, 2000. 280: p. 86-98. https://doi.org/10.1016/S0022-3115(00)00034-9
  16. Govers, K., et al., Molecular dynamics study of Xe bubble re-solution in $UO_{2}$. Journal of Nuclear Materials 2012. 420 p. 282-290. https://doi.org/10.1016/j.jnucmat.2011.10.010
  17. Verwerft, M., Multiple voltage electron probe microanalysis of fission gas bubbles in irradiated nuclear fuel. Journal of Nuclear Materials, 2000. 282: p. 97-111. https://doi.org/10.1016/S0022-3115(00)00421-9
  18. COMSOL Multiphysics Modeling Guide, Version 3.5a. 2008, COMSOL Inc.
  19. Wood, M.H. and J.R. Matthews, A simple operational gas release and swelling model. Part I: Intragranualar gas. Journal of Nuclear Materials, 1980. 91: p. 35-40. https://doi.org/10.1016/0022-3115(80)90029-X
  20. Booth, A.H., A method of calculating fission gas diffusion from $UO_{2}$ fuel and its application to the x-2-f loop test. 1957.
  21. Olander, D.R. and D. Wongsawaeng, Re-solution of fission gas - A review: Part I. Intragranular bubbles. Journal of Nuclear Materials, 2006. 354: p. 94-109. https://doi.org/10.1016/j.jnucmat.2006.03.010
  22. Ham, F.S., Theory of diffusion-limited precipitation. Journal of Physical Chemistry in Solids, 1958. 6: p. 335-351. https://doi.org/10.1016/0022-3697(58)90053-2
  23. Lösönen, P., Modelling intragranular fission gas release in irradiation of sintered LWR $UO_{2}$ fuel. Journal of Nuclear Materials, 2002. 304: p. 29-49. https://doi.org/10.1016/S0022-3115(02)00856-5
  24. Gulden, M.E., Migration of gas bubbles in irradiated uranium dioxide. Journal of Nuclear Materials, 1967. 23: p. 30-36. https://doi.org/10.1016/0022-3115(67)90128-6
  25. Cornell, R.M. and G.H. Bannister, Proc. British Ceramic Society, 1967. 7: p. 355.
  26. Baker, C., The fission gas bubble distribtion in uranium dioxide from high temperature irradiated SGHWR fuel pins. Journal of Nuclear Materials, 1977. 66: p. 283-291. https://doi.org/10.1016/0022-3115(77)90117-9
  27. Baker, C., The migration of intragrnular fisson gas bubbles in irradiated uranium dioxide. 1977. 71: p. 117-123.
  28. Matthews, J.R. and M.H. Wood, Modelling the transient behaviour of fission gas. Journal of Nuclear Materials, 1979. 84: p. 125-136. https://doi.org/10.1016/0022-3115(79)90156-9
  29. Wood, M.H. and J.R. Matthews, A model of fission gas release at high temperatures. Journal of Nuclear Materials, 1981. 102: p. 223-225. https://doi.org/10.1016/0022-3115(81)90563-8
  30. Evans, J.H., The role of directed bubble diffusion to grain boundaries in post-irradiation fission gas release from $UO_{2}$: a quantitative assessment. Journal of Nuclear Materials, 1996. 238: p. 175-182. https://doi.org/10.1016/S0022-3115(96)00452-7
  31. Cornell, R.M., M.V. Speight, and B.C. Masters, The role of bubbles in fission gas release from uranium dioxide. Journal of Nuclear Materials, 1969. 30: p. 170-178. https://doi.org/10.1016/0022-3115(69)90178-0
  32. Cornell, R.M., An electron microscope examination of matrix fission-gas bubbles in irradiated uranium dioxide. Journal of Nuclear Materials, 1971. 38: p. 319-328. https://doi.org/10.1016/0022-3115(71)90061-4
  33. Turnbull, J.A., The mobility of intragranular bubbles in uranium dioxide during irradiation. Journal of Nuclear Materials, 1976. 62: p. 325-328. https://doi.org/10.1016/0022-3115(76)90031-3
  34. Chkuaseli, V.F. and H. Matzke, Fission gas bubble behaviour in uranium dioxide. Journal of Nuclear Materials, 1993. 201: p. 92-96. https://doi.org/10.1016/0022-3115(93)90162-R
  35. Turnbull, J.A., et al., The diffusion coefficients of gaseous and volatile species during the irradiation of uranium oxide. Journal of Nuclear Materials, 1982. 107: p. 168-184. https://doi.org/10.1016/0022-3115(82)90419-6
  36. Turnbull, J.A., R.J. White, and C.A. Wise. The diffusion coefficient for fission gas atoms in uranium dioxide. in Technical Committee Meeting on Water Reactor Fuel Element Computer Modelling in Steady State, Transient and Accidental Conditions. 1988. Preston, England: International Atomic Energy Agency.
  37. Nichols, F.A., Kinetics of diffusional motion of pores in solids. A review. Journal of Nuclear Materials, 1969. 30: p. 143-165. https://doi.org/10.1016/0022-3115(69)90176-7
  38. Veshchunov, M.S. and V.E. Shestak, An advanced model for intragranular bubble diffusivity in irradiated $UO_{2}$ fuel. Journal of Nuclear Materials, 2008. 376: p. 174-180. https://doi.org/10.1016/j.jnucmat.2008.01.026
  39. Evans, J.H., Bubble diffusion to grain boundaries in $UO_{2}$, and metals during annealing: a new approach. Journal of Nuclear Materials, 1994. 210: p. 21-29. https://doi.org/10.1016/0022-3115(94)90218-6
  40. Report of the Co-ordinated Research Project on Fuel modelling at extended burnup - FUMEX. Vol. IAEATECDOC- 998. 1998: IAEA.
  41. White, R.J., R.C. Corcoran, and J.P. Barnes, A Summary of Swelling Data Obtained from the AGR/Halden Ramp Test Programme. 2006.
  42. Sartori, E., J. Killeen, and J.A.T. Turnbull, International Fuel Performance Experiments (IFPE) Database. 2010, OECD-NEA.
  43. Van Uffelen, P., et al. Development of a transient fission gas release model for TRANSURANUS. in Water Reactor Fuel Performance Meeting. 2008. Seoul, Korea.
  44. Di Marcello, V., et al., Extension of the TRANSURANUS plutonium redistribution model for fast reactor performance analysis. Nuclear Engineering and Design, 2011. submitted for publication.
  45. Lassmann, K., TRANSURANUS: a fuel rod analysis code ready for use. Journal of Nuclear Materials, 1992. 188: p. 295-302. https://doi.org/10.1016/0022-3115(92)90487-6

Cited by

  1. Implementation of effective-stress-function algorithm for nuclear fuel performance code vol.14, pp.5, 2013, https://doi.org/10.1007/s12541-013-0103-1