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Original Articles

Swelling in UO2 under conditions of gas release

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Pages 47-63 | Received 11 Mar 1974, Published online: 20 Aug 2006

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Read on this site (10)

Katsumi UNE & Shinji KASHIBE. (1990) Fission Gas Release during Post Irradiation Annealing of BWR Fuels. Journal of Nuclear Science and Technology 27:11, pages 1002-1016.
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Motoo Aoyama, Sadao Uchikawa, Kazuyoshi Miki, Kazuo Hiramoto & Renzo Takeda. (1984) A Conceptual Design of a Fuel Bundle for Extended Burnup in Boiling Water Reactors. Nuclear Technology 64:1, pages 19-25.
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Shan H. Chien, A. R. Wazzan & D. Okrent. (1983) GRABB—A Computer Code for Simulating Fission Gas Dispostion in Oxide Fuel During Fast Thermal Transient. Nuclear Technology 60:1, pages 69-83.
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Antonio Villalobos, A. R. Wazzan & D. Okrent. (1982) Analysis of Fission Gas Disposition in Light Water Reactor Steady-State Operation. Nuclear Technology 58:3, pages 492-510.
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G. Bandyopadhyay & J. A. Buzzell. (1980) The Role of Fission Gas and Fuel Melting in Fuel Response during Simulated Hypothetical Loss-of-Flow Transients. Nuclear Technology 47:1, pages 91-109.
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M.O. Tucker. (1980) Grain boundary porosity and gas release in irradiated UO2 . Radiation Effects 53:3-4, pages 251-255.
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H.J. Matzke. (1980) Gas release mechanisms in UO2—a critical review. Radiation Effects 53:3-4, pages 219-242.
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Articles from other publishers (56)

Francisco Rotea, Mauricio Exequiel Cazado & Alejandro Soba. (2024) A model of fuel pellet swelling and its relation with grain growth. Journal of Nuclear Materials 589, pages 154847.
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Bei Ye, Aaron Oaks, Shenyang Hu, Benjamin Beeler, Jeff Rest, Zhi-Gang Mei & Abdellatif Yacout. (2023) Integrated simulation of U-10Mo monolithic fuel swelling behavior. Journal of Nuclear Materials 583, pages 154542.
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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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Simon C. Middleburgh, William E. Lee & Michael J.D. Rushton. (2021) Structure and properties of amorphous uranium dioxide. Acta Materialia 202, pages 366-375.
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Larry K. Aagesen, Daniel Schwen, Michael R. Tonks & Yongfeng Zhang. (2019) Phase-field modeling of fission gas bubble growth on grain boundaries and triple junctions in UO2 nuclear fuel. Computational Materials Science 161, pages 35-45.
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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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Zupan Hu. (2018) Developments of analyses on grid-to-rod fretting problems in pressurized water reactors. Progress in Nuclear Energy 106, pages 293-299.
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Michael Tonks, David Andersson, Ram Devanathan, Roland Dubourg, Anter El-Azab, Michel Freyss, Fernando Iglesias, Katalin Kulacsy, Giovanni Pastore, Simon R. Phillpot & Michael Welland. (2018) Unit mechanisms of fission gas release: Current understanding and future needs. Journal of Nuclear Materials 504, pages 300-317.
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J. Noirot, I. Zacharie-Aubrun & T. Blay. (2018) Focused ion beam–scanning electron microscope examination of high burn-up UO2 in the center of a pellet. Nuclear Engineering and Technology 50:2, pages 259-267.
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Pekka Lösönen. (2017) On the effect of irradiation-induced resolution in modelling fission gas release in UO2 LWR fuel. Journal of Nuclear Materials 496, pages 140-156.
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Reeju Pokharel, Donald W. Brown, Bjørn Clausen, Darrin D. Byler, Timothy L. Ickes, Kenneth J. McClellan, Robert M. Suter & Peter Kenesei. (2017) Non-Destructive Characterization of UO 2+ x Nuclear Fuels . Microscopy Today 25:6, pages 42-47.
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Blas Pedro Uberuaga & David A. Andersson. (2015) Uranium vacancy mobility at the Σ5 symmetric tilt and Σ5 twist grain boundaries in UO2. Computational Materials Science 108, pages 80-87.
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Yi Cui, Shurong Ding, Yongzhong Huo, Canglong Wang & Lei Yang. (2013) An efficient numerical method for intergranular fission gas evolution under transient with piecewise boundary resolution. Journal of Nuclear Materials 443:1-3, pages 570-578.
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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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S. Banerjee & T.R. Govindan Kutty. 2012. Functional Materials. Functional Materials 387 466 .
M.S. Veshchunov & V.I. Tarasov. (2009) An advanced model for grain face diffusion transport in irradiated UO2 fuel. Part 1: Model formulation. Journal of Nuclear Materials 392:1, pages 78-84.
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A.R. Massih & K. Forsberg. (2008) Calculation of grain boundary gaseous swelling in UO2. Journal of Nuclear Materials 377:2, pages 406-408.
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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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Yang-Hyun Koo, Byung-Ho Lee & Dong-Seong Sohn. (2000) Analysis of fission gas release and gaseous swelling in UO2 fuel under the effect of external restraint. Journal of Nuclear Materials 280:1, pages 86-98.
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Pekka Lösönen. (2000) On the behaviour of intragranular fission gas in UO2 fuel. Journal of Nuclear Materials 280:1, pages 56-72.
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P.G. Lucuta, Hj. Matzke & I.J. Hastings. (1996) A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations. Journal of Nuclear Materials 232:2-3, pages 166-180.
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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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Y. Tsuboi, T. Ogata, M. Kinoshita & H. Saito. (1992) Mechanistic model of fission gas behavior in metallic fuel. Journal of Nuclear Materials 188, pages 312-318.
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Y. Tsuboi, T. Ogata, M. Kinoshita & H. Saito. 1992. Nuclear Materials for Fission Reactors. Nuclear Materials for Fission Reactors 312 318 .
C.T. Walker, P. Knappik & M. Mogensen. (1988) Concerning the development of grain face bubbles and fission gas release in UO2 fuel. Journal of Nuclear Materials 160:1, pages 10-23.
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Vera Haase, Hannelore Keller-Rudek, Livio Manes, Brigitte Schulz, Gustav Schumacher, Dieter Vollath & Heinz ZimmermannD. Vollath. 1986. U Uranium. U Uranium 1 205 .
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J. Rest. (1984) An improved model for fission product behavior in nuclear fuel under normal and accident conditions. Journal of Nuclear Materials 120:2-3, pages 195-212.
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A.R. Massih. (1983) Percolation model for bubble interlinkage in ceramic nuclear fuels. Journal of Nuclear Materials 119:1, pages 116-118.
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R.J. White & M.O. Tucker. (1983) A new fission-gas release model. Journal of Nuclear Materials 118:1, pages 1-38.
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M.C. Naik, A.R. Paul & K.N.G. Kaimal. (1981) Migration and trapping of fission xenon in urania-doped thoria. Journal of Nuclear Materials 96:1-2, pages 57-63.
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G. Bandyopadhyay, J.A. Buzzell & G.L. Hofman. (1980) Microstructural studies of irradiated mixed-oxide fuels subjected to multiple, mild thermal transients. Journal of Nuclear Materials 92:1, pages 51-66.
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J. Rest & S.M. Gehl. (1980) The mechanistic prediction of transient fission-gas release from LWR fuel. Nuclear Engineering and Design 56:1, pages 233-256.
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M.J.F. Notley & I.J. Hastings. (1980) A microstructure-dependent model for fission product gas release and swelling in UO2 fuel. Nuclear Engineering and Design 56:1, pages 163-175.
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J.C. Killeen. (1980) Fission gas release and swelling in UO2 doped with Cr2O3. Journal of Nuclear Materials 88:2-3, pages 177-184.
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M.O. Tucker. (1979) A simple description of interconnected grain edge porosity. Journal of Nuclear Materials 79:1, pages 199-205.
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M.O. Tucker. (1978) Relative growth rates of fission-gas bubbles on grain faces. Journal of Nuclear Materials 78:1, pages 17-23.
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I.J. Hastings, M.J.F. Notley & D.H. Rose. (1978) Irradiation-induced volume changes in commercial UO2 fuel: Comparison with model prediction. Journal of Nuclear Materials 75:2, pages 301-303.
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M.O. Tucker. (1978) The transfer of fission gas between grain faces and edges in UO2. Journal of Nuclear Materials 75:2, pages 282-287.
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M.O. Tucker. (1978) The spacing of intergranular fission gas bubbles in irradiated UO2. Journal of Nuclear Materials 74:1, pages 34-40.
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