Keywords: 28.41 ب.م; 25.85.Ec; 28.41.Bm; 28.41.Rc; 29.40.Wk;
مقالات ISI 28.41 ب.م (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.
Microstructural changes induced by low energy heavy ion irradiation in titanium silicon carbide
Keywords: 28.41 ب.م; 81.05.Je; 61.80.Lj; 25.75.Ag; 28.41.Bm; 68.37.Ps; 61.05.J−Ti3SiC2; Nuclear interaction; Electron back-scatter diffraction; Atomic force microscopy; Anisotropic swelling
New concept of designing Pu and MA containing fuel for fast reactors
Keywords: 28.41 ب.م; 28.41.Bm; 68.08.−p; 61.66.Dk
Oxygen potentials of mixed oxide fuels for fast reactors
Keywords: 28.41 ب.م; 28.41.Bm; 28.50.Ft; 65.40.-b;
Pressurized heavy water reactor fuel behaviour in power ramp conditions
Keywords: 28.41 ب.م; 06.30.Bp; 06.60.Ei; 28.41.Bm; 28.41.Qb; 46.50._a; 61.82.Bg; 62.20.mm; 61.66._f; 68.47.De; 81.70.Tx
Thermal conductivities of americium dioxide and sesquioxide by molecular dynamics simulations
Keywords: 28.41 ب.م; 28.41.Bm; 28.41.Ak; 05.70.âa; 82.60.âs; Americium oxide; Thermal conductivity; Thermal expansion; Molecular dynamics simulations;
Spark Plasma Sintering of simulated radioisotope materials within tungsten cermets
Keywords: 28.41 ب.م; 07.77.−n; 07.87.+V; 25.85.Ca; 28.90.+i; 28.41.Bm; 28.41.Kw; 28.50.Hw; 28.50.Ky
Evaluation of melting point of UO2 by molecular dynamics simulation
Keywords: 28.41 ب.م; 28.41.Bm; 28.41.Ak; 05.70.−a; 82.60.−s
Behavior of Si impurity in Np-Am-MOX fuel irradiated in the experimental fast reactor Joyo
Keywords: 28.41 ب.م; 28.41.Bm;
Radial redistribution of actinides in irradiated FR-MOX fuels
Keywords: 28.41 ب.م; 28.41.Bm
Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation
Keywords: 28.41 ب.م; 28.20.Fc; 28.41.Bm; 66.30.−h; 32.80.−t; 81.65.Mq
Analytical investigations of irradiated inert matrix fuel
Keywords: 28.41 ب.م; 28.41.Bm; 28.41.Vx; 28.65.+a; 68.35.Fx; 68.37.Hk; 68.37.Yz
Design of a fuel element for a lead-cooled fast reactor
Keywords: 28.41 ب.م; 28.41.−i; 28.41.Ak; 28.41.Bm; 28.50.Ft
Oxygen potential of hypo-stoichiometric Lu-doped UO2
Keywords: 28.41 ب.م; 28.41.Bm;
Ion beam analysis of materials in the PBMR reactor
Keywords: 28.41 ب.م; 28.41.−i; 28.41.Bm; 28.50.−k; 28.52.Fa; 61.72.Hh; 61.80.−x; 61.80.Hg; 61.80.Jh; 61.72.YxIon beam analysis; Nuclear fission reactor; Materials; RBS; Channeling
Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor
Keywords: 28.41 ب.م; 28.41.Bm; 28.50.âk; 28.52.Fa; 81.05.Je; 81.15.Gh;
Equilibrium and nonequilibrium molecular dynamics simulations of heat conduction in uranium oxide and mixed uranium-plutonium oxide
Keywords: 28.41 ب.م; 28.41.Bm; 28.52.Av; 44.10.+i; 71.15.Pd;
Advanced characterization techniques for SiC and PyC coatings on high-temperature reactor fuel particles
Keywords: 28.41 ب.م; 61.10.−i; 61.14.−x; 68.37.−d; 61.72.Qq; 68.55.Ln; 68.55.Nq; 28.41.Bm
Microchemical study of high-burnup CANDU® fuel by imaging-XPS
Keywords: 28.41 ب.م; 81.70; 28.41.Bm;
A method for the quantification of total xenon concentration in irradiated nuclear fuel with SIMS and EPMA
Keywords: 28.41 ب.م; 28.41.Bm; 39.10.+jSIMS; EPMA; Xenon; Irradiated nuclear fuel; Fission gas release
Increase in pyrolytic carbon optical anisotropy and density during processing of coated particle fuel due to heat treatment
Keywords: 28.41 ب.م; 28.41.Bm; 28.52.Fa; 42.25.Ja; 81.40.Gh
Optical anisotropy measurements of TRISO nuclear fuel particle cross-sections: The method
Keywords: 28.41 ب.م; 28.41.Bm; 42.25.Ja; 78.67.−n
Automated optical microscopy of coated particle fuel
Keywords: 28.41 ب.م; 07.60.Pb; 28.41.Bm
Enhanced thermal conductivity oxide nuclear fuels by co-sintering with BeO: II. Fuel performance and neutronics
Keywords: 28.41 ب.م; 28.41.Bm; 89.30.Gg
Selection of water-dispersible carbon black for fabrication of uranium oxicarbide microspheres
Keywords: 28.41 ب.م; 81.05.Uw; 82.70.−y; 68.43.−h; 28.41.Bm
Detailed characterisations of high burn-up structures in oxide fuels
Keywords: 28.41 ب.م; 28.41.Bm; 81.05.Je;
Simulation of γ-ray spectrometry of failed TRISO fuel
Keywords: 28.41 ب.م; 28.41.Bm; 07.85.Fv; 28.41.âi; Very high temeprature reactor; TRISO; Fuel failure; Fission product release; Monte Carlo; γ-ray spectrometry;
Analysis of the impact of random summing on passive assay of pebble bed reactor fuel using gamma-ray spectrometry
Keywords: 28.41 ب.م; 28.41.Bm; 07.85.Fv; 28.41.−iPebble bed reactor; Burnup; Nuclear fuel; Gamma-ray; Spectrometry; Monte Carlo; Germanium detector; Random summing
Pu-breeding feasibility in PWR
Keywords: 28.41 ب.م; 89.30.Gg; 28.41.Bm
Dispersion type zirconium matrix fuels fabricated by capillary impregnation method
Keywords: 28.41 ب.م; 28.41.Bm; 81.05.Zx; 81.05.Rm
Prediction of oxygen potential in americium thorium oxides phase of a cermet fuel
Keywords: 28.41 ب.م; 28.41.Bm
Production of 242mAm
Keywords: 28.41 ب.م; 27.90.+b; 28.41.Bm; 28.80+s242mAm; Nuclear fuel; Enrichment
Concept of an accelerator-driven subcritical research reactor within the TESLA accelerator installation
Keywords: 28.41 ب.م; 29.20.Hm; 28.41.âi; 28.41.Ak; 28.41.Bm; Cyclotrons; Accelerator-driven systems; Fuel elements;
Fuels for accelerator-driven systems
Keywords: 28.41 ب.م; 28.41.Bm; 28.50.FtTransmutation; Minor actinide fuels; Accelerator-driven systems
Fabrication and characterization of dual phase magnesia-zirconia ceramics doped with plutonia
Keywords: 28.41 ب.م; C0300; F0700; O0200; P0700; P1000; 28.41.Bm; 81.05.Je; 81.05.Mh; 28.41.Kw;
Neutronic double heterogeneity effect in particle dispersed type inert matrix fuels
Keywords: 28.41 ب.م; C0600; C0900; F0700; M0200; P0700; T0200; 28.41.Ak; 28.41.Bm; 28.50.Hw;
On stability of spatial distributions of crystal structure defects in irradiated high burnup UO2 fuel
Keywords: 28.41 ب.م; F0700; R0200; T0100; U0200; 28.41.Bm; 61.80.Az;
Evaluation of thermal conductivity of zirconia-based inert matrix fuel by molecular dynamics simulation
Keywords: 28.41 ب.م; F0700; M0200; O0200; T060071.15.Pd; 28.41.Bm; 44.10.+i
Inert matrix fuel behaviour in test irradiations
Keywords: 28.41 ب.م; F0700; O0200; P0700; R0400; T0700; Z0200; 28.41.Bm; 81.05.Je; 81.05.Mh;
Critical review of carbon monoxide pressure measurements in the uranium–carbon–oxygen ternary system
Keywords: 28.41 ب.م; C0400; F0700; P0200; T0400; U020081.05.Je; 81.30.Dz; 82.60.Hc; 07.30.Dz; 28.41.Bm
Recycling of chemicals from alkaline waste generated during preparation of UO3 microspheres by sol–gel process
Keywords: 28.41 ب.م; P1300; U0200; W010081.20.Fw; 28.41.Bm; 28.41.Kw; 82.39.Wj
Separation of plutonium from lanthanum by electrolysis in LiCl-KCl onto molten bismuth electrode
Keywords: 28.41 ب.م; P0700; 81.15.Pq; 28.41.Bm;
Distillation of cadmium from uranium-plutonium-cadmium alloy
Keywords: 28.41 ب.م; P0700; P1300; U0100; 28.41.Bm; 81.20.Ym; 82.30.Lp; 81.05.Bx;
Fission gas release in FBR MOX fuel irradiated to high burnup
Keywords: 28.41 ب.م; F0500; F0700; N0100; P0700; U0200; 28.41.Bm;
Chlorination of UO2, PuO2 and rare earth oxides using ZrCl4 in LiCl-KCl eutectic melt
Keywords: 28.41 ب.م; C0400; P0700; R0700; R1300; U0200; 28.41.Bm; 82.40.âg;
Dual phase MgO-ZrO2 ceramics for use in LWR inert matrix fuel
Keywords: 28.41 ب.م; C0300; F0700; P1300; T0200; 28.41.Bm; 81.05.Je; 81.05.Mh; 28.41.Kw;