Open Access
EPJ Nuclear Sci. Technol.
Volume 2, 2016
Article Number 19
Number of page(s) 7
Published online 15 April 2016
  1. M.D. Freshley, D.W. Brite, J.L. Daniel, P.E. Hart, Irradiation-induced densification of UO2 pellet fuel, J. Nucl. Mater. 62 , 138 (1976) [CrossRef] [Google Scholar]
  2. G. Maier, H. Assmann, W. Dorr, Resinter testing in relation to in-pile densification, J. Nucl. Mater. 153 , 213 (1988) [CrossRef] [Google Scholar]
  3. H. Stehle, H. Assmann, The dependence of in-reactor UO2 densification on temperature and microstructure, J. Nucl. Mater. 52 , 303 (1974) [CrossRef] [Google Scholar]
  4. M.S. Veshchunov, V.D. Ozrin, V.E. Shestak, V.I. Tarasov, R. Dubourg, G. Nicaise, Development of mechanistic code MFPR for modelling fission product release from irradiated UO2 fuel, Nucl. Eng. Des. 236 , 179 (2006) [CrossRef] [Google Scholar]
  5. M.S. Veshchunov, R. Dubourg, V.D. Ozrin, V.E. Shestak, V.I. Tarasov, Mechanistic modeling of urania fuel evolution and fission product migration during irradiation and heating: the MFPR code, J. Nucl. Mater. 362 , 327 (2007) [CrossRef] [Google Scholar]
  6. B. Burton, G.L. Reynolds, The sintering of grain boundary cavities in uranium dioxide, J. Nucl. Mater. 45 , 10 (1972) [CrossRef] [Google Scholar]
  7. R.J. White, M.O. Tucker, A new fission-gas release model, J. Nucl. Mater. 118 , 1 (1983) [CrossRef] [Google Scholar]
  8. V.I. Tarasov, M.S. Veshchunov, Models for fuel porosity evolution in UO2 under various regimes of reactor operation, Nucl. Eng. Des. 272 , 65 (2014) [CrossRef] [Google Scholar]
  9. Y. Harada, S. Doi, Irradiation behavior of large grain UO2 fuel rod by active powder, J. Nucl. Sci. Tech. 35 , 411 (1998) [CrossRef] [Google Scholar]
  10. C.C. Dollins, F.A. Nichols, In-pile intragranular densification of oxide fuels, J. Nucl. Mater. 78 , 326 (1978) [CrossRef] [Google Scholar]
  11. M.V. Speight, W. Beere, Vacancy potential and void growth on grain boundaries, Metal Sci. 9 , 190 (1975) [CrossRef] [Google Scholar]
  12. G. Maier, H. Assmann, W. Dorr, Resinter testing in relation to in-pile densification, J. Nucl. Mater. 153 , 213 (1988) [CrossRef] [Google Scholar]
  13. G.L. Reynolds, B. Burton, Grain-boundary diffusion in uranium dioxide: The correlation between sintering and creep and a reinterpretation of creep mechanism, J. Nucl. Mater. 82 , 22 (1979) [CrossRef] [Google Scholar]
  14. S. Yamagishi, T.J. Tanifuji, Post-irradiation studies on knock-out and pseudo-recoil releases of fission products from fissioning UO2, J. Nucl. Mater. 59 , 243 (1976) [CrossRef] [Google Scholar]
  15. S. Schlutig, Contribution à l’étude de la pulvérisation et de l’endommagement du dioxyde d’uranium par les ions lourds rapides, PhD Thesis, University of Caen, 2001 [Google Scholar]
  16. M.O. Marlowe, In-reactor densification behavior of UO2, NEDO-12440, 1973 [Google Scholar]
  17. Y. Irisa, Y. Takada, in ANS Topical Meeting , Williamsburg (1988) [Google Scholar]
  18. S. Doi, S. Abeta, Y. Irisa, S. Inoue, in ANS Topical Meeting , Avignon, France (1991) [Google Scholar]
  19. R.S. Nelson, The stability of gas bubbles in an irradiation environment, J. Nucl. Mater. 31 , 153 (1969) [CrossRef] [Google Scholar]
  20. V.I. Tarasov, M.S. Veshchunov, An advanced model for grain face diffusion transport in irradiated UO2 fuel. Part 2. Model Implementation and validation, J. Nucl. Mater. 392 , 84 (2009) [CrossRef] [Google Scholar]
  21. M.S. Veshchunov, V.I. Tarasov, An advanced model for grain face diffusion transport in Irradiated UO2 fuel. Part 1. Model formulation, J. Nucl. Mater. 392 , 78 (2009) [CrossRef] [Google Scholar]
  22. M.S. Veshchunov, V.I. Tarasov, Modelling of irradiated UO2 fuel behaviour under transient conditions, J. Nucl. Mater. 437 , 250 (2013) [CrossRef] [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.