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Original Articles

A review of irradiation induced re-solution in oxide fuels

Pages 243-249 | Published online: 19 Aug 2006

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Ki-Seob Sim, Ho Chun Suk & Young Ku Yoon. (1992) A Computer Model for Predicting Transient Fission Gas Release from UO2 Fuel. Nuclear Technology 99:3, pages 351-365.
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Hj. Matzke. (1982) Radiation damage in crystalline insulators, oxides and ceramic nuclear fuels. Radiation Effects 64:1-4, pages 3-33.
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Articles from other publishers (25)

G. Pastore, N. Militello, S. Blondel & B.D. Wirth. (2023) Single-size and cluster dynamics modeling of intra-granular fission gas bubbles in UO . Journal of Nuclear Materials 583, pages 154453.
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Feipeng Qi, Wenjie Li, Zhenhai Liu, Quan Li, Yuanming Li, YongZhong Huang, Bo Zhao, Yile Zhang & Chenxi Li. (2022) Gradient percolation of fission gases in nuclear fuel pellet. Journal of Nuclear Materials 571, pages 153993.
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Paul Van Uffelen & Giovanni Pastore. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 363 416 .
J. Rest, M.W.D. Cooper, J. Spino, J.A. Turnbull, P. Van Uffelen & C.T. Walker. (2019) Fission gas release from UO2 nuclear fuel: A review. Journal of Nuclear Materials 513, pages 310-345.
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D. Salvato, A. Leenaers, S. Van den Berghe & C. Detavernier. (2018) Pore pressure estimation in irradiated UMo. Journal of Nuclear Materials 510, pages 472-483.
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G. Pastore, D. Pizzocri, C. Rabiti, T. Barani, P. Van Uffelen & L. Luzzi. (2018) An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution. Journal of Nuclear Materials 509, pages 687-699.
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Christopher Matthews, Daniel Schwen & Andrew C. Klein. (2015) Radiation re-solution of fission gas in non-oxide nuclear fuel. Journal of Nuclear Materials 457, pages 273-278.
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M.S. Veshchunov & V.I. Tarasov. (2013) Modelling of irradiated UO2 fuel behaviour under transient conditions. Journal of Nuclear Materials 437:1-3, pages 250-260.
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Yi Cui, Yongzhong Huo, Shurong Ding, Lin Zhang & Yuanming Li. (2012) An analytical solution for simulation of the fission gas behaviors with time-dependent piece-wise boundary resolution. Journal of Nuclear Materials 424:1-3, pages 109-115.
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K. Govers, C.L. Bishop, D.C. Parfitt, S.E. Lemehov, M. Verwerft & R.W. Grimes. (2012) Molecular dynamics study of Xe bubble re-solution in UO2. Journal of Nuclear Materials 420:1-3, pages 282-290.
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K. Govers, S.E. Lemehov & M. Verwerft. (2010) On the solution and migration of single Xe atoms in uranium dioxide – An interatomic potentials study. Journal of Nuclear Materials 405:3, pages 252-260.
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Paul Van Uffelen, Rudy J. M. Konings, Carlo Vitanza & James Tulenko. 2010. Handbook of Nuclear Engineering. Handbook of Nuclear Engineering 1519 1627 .
David C. Parfitt & Robin W. Grimes. (2009) Predicting the probability for fission gas resolution into uranium dioxide. Journal of Nuclear Materials 392:1, pages 28-34.
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K. Govers, S. Lemehov & M. Verwerft. (2008) In-pile Xe diffusion coefficient in UO2 determined from the modeling of intragranular bubble growth and destruction under irradiation. Journal of Nuclear Materials 374:3, pages 461-472.
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K Forsberg & A R Massih. (2007) Kinetics of fission product gas release during grain growth. Modelling and Simulation in Materials Science and Engineering 15:3, pages 335-353.
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John D. B. Lambert & Robert Strain. 2006. Materials Science and Technology. Materials Science and Technology.
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P. Van Uffelen. (2000) Modelling the variable precipitation of fission products at grain boundaries. Journal of Nuclear Materials 280:3, pages 275-284.
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M.S. Veshchunov. (2000) On the theory of fission gas bubble evolution in irradiated UO2 fuel. Journal of Nuclear Materials 277:1, pages 67-81.
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S. E. Donnelly, R. C. Birtcher, C. Templier & V. Vishnyakov. (1995) Response of helium bubbles in gold to displacement-cascade damage. Physical Review B 52:6, pages 3970-3975.
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William H. Hocking, A.Michael Duclos & Lawrence H. Johnson. (1994) Study of fission-product segregation in used CANDU fuel by X-ray photoelectron spectroscopy (XPS) II. Journal of Nuclear Materials 209:1, pages 1-26.
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J. H. Evans. 1991. Fundamental Aspects of Inert Gases in Solids. Fundamental Aspects of Inert Gases in Solids 307 319 .
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M. Mogensen, C.T. Walker, I.L.F. Ray & M. Coquerelle. (1985) Local fission gas release and swelling in water reactor fuel during slow power transients. Journal of Nuclear Materials 131:2-3, pages 162-171.
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