Keywords: انتشار گازهای شکافت; Nuclear fuel performance; Intragranular fission gas atom transport; Diffusion; Drift; Fission gas release;
مقالات ISI انتشار گازهای شکافت (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
Keywords: انتشار گازهای شکافت; Spent nuclear fuel; Static leaching; Instant release fraction; FIRST-Nuclides; FGR; Fission gas release; IRF; Instant release fraction; LPR; Linear power rating; SNF; Spent nuclear fuel;
Keywords: انتشار گازهای شکافت; Fission gas release; Grain boundary networks; Crystallographic consistency; Bubble percolation;
Keywords: انتشار گازهای شکافت; Gamma tomography; Fission gas release; Nondestructive measurements;
Focused ion beam-scanning electron microscope examination of high burn-up UO2 in the center of a pellet
Keywords: انتشار گازهای شکافت; Electron BackScattered Diffraction; Fission Gas Bubbles; Fission Gas Release; Focused Ion Beam-Scanning Electron Microscope; Grain; High Burn-Up; UO2;
The fuel behaviour code FUROM and its high burn-up simulation capabilities
Keywords: انتشار گازهای شکافت; Fuel behaviour; Fission gas release; Thermo-mechanical response; VVER fuel, FUROM;
Qualification of the MEXIICO loop dedicated to nuclear power transients: An experimental and modelling approach
Keywords: انتشار گازهای شکافت; MEXIICO furnace; CFD; Compressible fluid; Gas depressurization; Fission gas release;
Application of the BEPU methodology to assess fuel performance in dry storage
Keywords: انتشار گازهای شکافت; BE; best estimate; BEPU; Best Estimate Plus Uncertainty; CHS; cladding hoop stress in dry storage (MPa); EOL; end-of-reactor-life; FGR; fission gas release; NRC; Nuclear Regulatory Commission; PDF; probabilistic distribution function; PNNL; Pacific Northw
The influence of cladding on fission gas release from irradiated U-Mo monolithic fuel
Keywords: انتشار گازهای شکافت; Uranium-molybdenum; Fission gas release; Thermal analysis; Irradiation;
Irradiation performance of (Th,Pu)O2 fuel under Pressurized Water Reactor conditions
Keywords: انتشار گازهای شکافت; Thorium fuel; Irradiation performance; Fission gas release;
Experimental investigation on the causes for pellet fragmentation under LOCA conditions
Keywords: انتشار گازهای شکافت; Nuclear fuel; LOCA; Fragmentation; Fission gas release; Halden Reactor Project;
INFLUENCE OF FUEL-MATRIX INTERACTION ON THE BREAKAWAY SWELLING OF U-MO DISPERSION FUEL IN AL
Keywords: انتشار گازهای شکافت; U-Mo; Dispersion Fuel; Breakaway Swelling; Fuel-matrix Interaction; Fission Gas Release
Modeling RIA benchmark cases with FRAPTRAN and SCANAIR: A comparative exercise
Keywords: انتشار گازهای شکافت; CEA; Comisariat à l'Energie Atomique et aux Energies Alternatives; CIEMAT; Centro de Investigaciones Energéticas Medioambientales y Tecnológicas; CSED; critical strain energy density; CSN; Consejo de Seguridad Nuclear; EDF; Electricité De France; EN
Application of advanced validation concepts to oxide fuel performance codes: LIFE-4 fast-reactor and FRAPCON thermal-reactor fuel performance codes
Keywords: انتشار گازهای شکافت; AISI; American Iron and Steel Institute; EBR-II; Experimental Breeder Reactor-II; FCAS; fuel column axial strain; FCHR; fuel central hole radius; FCMI; fuel cladding mechanical interaction; FCZR; fuel column zone radius; FEZR; fuel equiaxed zone radius; F
Percolation on grain boundary networks: Application to fission gas release in nuclear fuels
Keywords: انتشار گازهای شکافت; Percolation; Fission gas release; Grain boundary; Nuclear fuel; Intergranular bubbles;
Steady-state fuel behavior modeling of nitride fuels in FRAPCON-EP
Keywords: انتشار گازهای شکافت; TD; theoretical density; HM; heavy metal; FGR; fission gas release; BOC; beginning-of-cycle; MOC; middle-of-cycle; EOC; end-of-cycle; LOCA; Loss of Coolant Accident; SD; standard deviation; AE; average fractional error; EOL; end-of-life;
Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project
Keywords: انتشار گازهای شکافت; BI; base irradiation; BWR; boiling water reactor; DHC; delayed hydride cracking; EPRI; Electric Power Research Institute; FGR; fission gas release; HE; hydrogen embrittlement; KKL; Kernkraftwerk Leibstadt; LOCA; loss of coolant accident; LWR; light water
Under irradiation issues of the CSZ–based inert matrix fuels from IFA-652 Halden experiment
Keywords: انتشار گازهای شکافت; Inert Matrix Fuel; Fission Gas Release; Fuel Rod Performance Code
Defect energetics and Xe diffusion in UO2UO2 and ThO2ThO2
Keywords: انتشار گازهای شکافت; Formation energy; Migration energy; Resistance against oxidation; Fission gas release; Vacancy-assisted mechanism
A method for the quantification of total xenon concentration in irradiated nuclear fuel with SIMS and EPMA
Keywords: انتشار گازهای شکافت; 28.41.Bm; 39.10.+jSIMS; EPMA; Xenon; Irradiated nuclear fuel; Fission gas release