Under irradiation issues of the CSZ–based inert matrix fuels from IFA-652 Halden experiment
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[1] T. Tverberg,et al. Inert Matrix Fuel Analysis by Means of the TRANSURANUS Code : The Halden IFA-652 In-Pile Test , 2009 .
[2] L. Luzzi,et al. Thoria and inert matrix fuels for a sustainable nuclear power , 2008 .
[3] T. Ogawa,et al. Fuel performance evaluation of rock-like oxide fuels , 2008 .
[4] P. Blair,et al. Inert matrix fuel behaviour in test irradiations , 2006 .
[5] T. Tverberg,et al. Inert matrix and thoria fuel irradiation at an international research reactor , 2006 .
[6] C. Hellwig,et al. Yttrium stabilised zirconia inert matrix fuel irradiation at an international research reactor , 2006 .
[7] Claude Degueldre,et al. Thermophysical Properties of Inert Matrix Fuels for Actinide Transmutation. , 2003 .
[8] K. Lassmann,et al. Analysis of fuel centre temperatures with the TRANSURANUS code , 2003 .
[9] G. Ledergerber,et al. Inert matrix fuel for the utilisation of plutonium , 2002 .
[10] C. Lombardi. Inert matrix and thoria fuels for plutonium elimination , 2002 .
[11] Marco Enrico Ricotti,et al. Neutronic analysis of U-free inert matrix and thoria fuels for plutonium disposition in pressurised water reactors , 1999 .
[12] S. Coelli,et al. Preliminary fabrication and characterisation of inert matrix and thoria fuels for plutonium disposition in light water reactors , 1999 .
[13] C. Degueldre,et al. Control of civilian plutonium inventories using burning in a non-fertile fuel , 1997 .
[14] K. Lassmann,et al. TRANSURANUS: a fuel rod analysis code ready for use , 1992 .
[15] K. Lassmann,et al. URANUS — A computer programme for the thermal and mechanical analysis of the fuel rods in a nuclear reactor , 1978 .