Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials
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[1] P. Jha,et al. Dependence of strain on the thermoelectric properties of Uranium Carbide , 2020 .
[2] A. Y. Soliman,et al. Thermal-hydraulic and solid mechanics safety analysis for VVER-1000 reactor using analytical and CFD approaches , 2020 .
[3] M. Kazimi,et al. Nuclear Systems Volume I , 2020 .
[4] S. Talebi,et al. Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS , 2020 .
[5] D. R. Costa,et al. UN microspheres embedded in UO2 matrix: An innovative accident tolerant fuel , 2020, Journal of Nuclear Materials.
[6] C. Deng,et al. Preparation of tetragonal zirconia microspheres as surrogate precursor for uranium nitride microspheres , 2020 .
[7] K. Terrani,et al. Uranium nitride tristructural-isotropic fuel particle , 2020 .
[8] A. Zolfaghari,et al. A coupled neutronic/thermal–hydraulic module for the transient analysis of VVER-1000 reactor during reactivity insertion accidents , 2020 .
[9] A. Zolfaghari,et al. Evaluation of accident tolerant cladding materials in a severe accident of the BNPP , 2019, Annals of Nuclear Energy.
[10] A. Qteish,et al. Thermal neutron scattering kernels for uranium mono-nitride: A potential advanced tolerant fuel candidate for light water reactors , 2019, Annals of Nuclear Energy.
[11] A. Galahom. Improvement of the VVER-1200 Fuel Cycle by Introducing Thorium with Different Fissile Material in Blanket-Seed Assembly , 2019, Nuclear Science and Engineering.
[12] Wei Zhou,et al. Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review , 2018, Annals of Nuclear Energy.
[13] F. Faghihi,et al. Neutronics and sub-channel thermal-hydraulics analysis of the Iranian VVER-1000 fuel bundle , 2016 .
[14] V. G. Baranov,et al. A physical model for evaluating uranium nitride specific heat , 2013 .
[15] F. Faghihi,et al. Shut-down margin study for the next generation VVER-1000 reactor including 13 × 13 hexagonal annular assemblies ☆ , 2011 .
[16] F. Faghihi,et al. Modified COBRA-EN code to investigate thermal-hydraulic analysis of the Iranian VVER-1000 core , 2010 .
[17] J. K. Fink,et al. Thermophysical properties of uranium dioxide , 2000 .
[18] J. Routbort,et al. Elastic, diffusional, and mechanical properties of carbide and nitride nuclear fuels — a review , 1975 .
[19] V. G. Baranov,et al. Thermal stability investigation technique for uranium nitride , 2016 .
[20] P. Werner,et al. Mechanical Properties of Advanced Fuels Under Compressive Deformation , 1981 .
[21] J. A. Leary,et al. MECHANICAL PROPERTIES OF CARBIDE AND NITRIDE REACTOR FUELS. , 1970 .