Towards the inclusion of open fabrication porosity in a fission gas release model

[1]  P. V. Uffelen,et al.  Modelling actinide redistribution in mixed oxide fuel for sodium fast reactors , 2014 .

[2]  M. Kazimi,et al.  Steady-state fuel behavior modeling of nitride fuels in FRAPCON-EP , 2012 .

[3]  Michael R. Tonks,et al.  Grain boundary percolation modeling of fission gas release in oxide fuels , 2012 .

[4]  Paul C. Millett,et al.  PERCOLATION ON GRAIN BOUNDARY NETWORKS: APPLICATION TO FISSION GAS RELEASE IN NUCLEAR FUELS , 2012 .

[5]  K. Maeda,et al.  Short-term irradiation behavior of low-density americium-doped uranium–plutonium mixed oxide fuels irradiated in a fast reactor , 2011 .

[6]  K. Maeda,et al.  Radial redistribution of actinides in irradiated FR-MOX fuels , 2009 .

[7]  T. Iwai,et al.  Fission gas release and swelling in uranium–plutonium mixed nitride fuels , 2004 .

[8]  Yongsoo Kim,et al.  Theoretical analysis of two-stage fission gas release processes: grain lattice and grain boundary diffusion , 2004 .

[9]  R. J. White,et al.  The development of grain-face porosity in irradiated oxide fuel , 2004 .

[10]  J. Jacoud,et al.  An efficient model for the analysis of fission gas release , 2002 .

[11]  Keon-Sik Kim,et al.  Reduction of the open porosity of UO2 pellets through pore structure control , 2000 .

[12]  Yang-Hyun Koo,et al.  Cosmos: A computer code to analyze LWR UO2 and MOX fuel up to high burnup , 1999 .

[13]  G. Nicolaou,et al.  Transmutation of neptunium and americium in a fast neutron flux: EPMA results and KORIGEN predictions for the superfact fuels , 1995 .

[14]  K. Lassmann,et al.  TRANSURANUS: a fuel rod analysis code ready for use , 1992 .

[15]  N. Matsunaga,et al.  Determination of the thermal conductivity of xenon-helium mixtures at high temperatures by the shock-tube method , 1992 .

[16]  A. R. Massih,et al.  Diffusion theory of fission gas migration in irradiated nuclear fuel UO2 , 1985 .

[17]  R. J. White,et al.  A new fission-gas release model , 1983 .

[18]  W. Hering The kwu fission gas release model for lwr fuel rods , 1983 .

[19]  F. A. Johnson,et al.  The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide , 1982 .

[20]  H. Matzke,et al.  Gas release mechanisms in UO2—a critical review , 1980 .

[21]  Boon Wong,et al.  Models for Kinetics of Solid State Sintering , 1979 .

[22]  Donald R. Olander,et al.  Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .

[23]  V. W. Storhok,et al.  MIXED-NITRIDE FUEL IRRADIATION PERFORMANCE. , 1971 .

[24]  M. V. Speight,et al.  A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation , 1969 .

[25]  E. Thornton Viscosity and Thermal Conductivity of Binary Gas Mixtures: Krypton-Argon, Krypton-Neon, and Krypton-Helium , 1961 .

[26]  R. L. Coble,et al.  Sintering Crystalline Solids. I. Intermediate and Final State Diffusion Models , 1961 .

[27]  A. H. Booth A METHOD OF CALCULATING FISSION GAS DIFFUSION FROM UO$sub 2$ FUEL AND ITS APPLICATION TO THE X-2-f LOOP TEST , 1957 .