مقالات ISI (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
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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.
Feasibility of the electrochemical way in molten fluorides for separating thorium and lanthanides and extracting lanthanides from the solvent
Keywords: A0200; C0400; M0400; T0700
Burnup simulations and spent fuel characteristics of ZrO2 based inert matrix fuels
Keywords: A0200; F0700; M0200; N0500; W0200; Z0200;
Linear free energy relationship applied to trivalent cations with lanthanum and actinium oxide and hydroxide structure
Keywords: A0200; F0700; T0400
Thermal diffusivity of Americium mononitride from 373 to 1473 K
Keywords: A0200; E0500; F0700; T060065.40.−b; 81.05. Je
Assessment of americium and curium transmutation in magnesia based targets in different spectral zones of an experimental accelerator driven system
Keywords: A0200; F0700; M0100; P0700; T010028.41.Bm; 28.41.Kw
Amorphization of β-thorium phosphate diphosphate (β-TPD) irradiated with high energy krypton ions
Keywords: A0200; A0600; C0300; I0400; R0200; R0800; T0700; W0100;
Oxygen potential of (Pu0.91Am0.09)O2−x
Keywords: A0200; P0700; T040028.41.Bm
Plutonium incorporation in phosphate and titanate ceramics for minor actinide containment
Keywords: A0200; C0300; I0600; P0700; W010081.05.Je; 61.82−d
A computationally simple model for determining the time dependent spectral neutron flux in a nuclear reactor core
Keywords: A0200; F0700; M0200; N0500; P0700; U0200
Irradiation stability of R7T7-type borosilicate glass
Keywords: A0200; A0600; R0300; R0400; W020028.41.Kw; 61.43.Fs; 81.05.Kf
An experimental study of the dissolution rates of Nd-britholite, an apatite-structured actinide-bearing waste storage host analogue
Keywords: A0200; C0300; C0800; W0200
Oxygen potential measurements of fluorite-type Zr0.5Pu0.5O2ây by EMF method
Keywords: A0200; O0200; P0700; T0400;
Molecular dynamics studies of actinide nitrides
Keywords: A0200; M0200; P0700; T0400; T0600; T0700; U0200;
Thermodynamic analysis on the Np-Zr-H system
Keywords: A0200; F0700; H0400; T0400;
Thermodynamic modelling of the (U, Pu, Np)O2±x mixed oxide
Keywords: A0200; O0200; T0400;
Calculation of enthalpies of formation of actinide nitrides
Keywords: A0200; T0400;
Phase equilibria and thermal expansion of CaTiO3 doped with neptunium
Keywords: A0200; T0600; W0100;
Low-temperature heat capacity measurements on encapsulated transuranium samples
Keywords: A0200; P0300; P0700; T0400; 65.40.+g; 75.40.Cx;
Extraction behavior of actinides and lanthanides in a molten fluoride/liquid aluminum system
Keywords: A0200; R0700; R1100;
Non-monotonic systematic variation of the thermodynamic properties of lanthanide metals in liquid bismuth
Keywords: A0200; L0300; R0700; T0400;
Fabrication and electrochemical behavior of nitride fuel for future applications
Keywords: A0200; C0400; P0700; P1000; T0400;
Determination of the ionization energy of NpO2 and comparative ionization energies of actinide oxides
Keywords: A0200; P0700; T0400; U0200;
A computational tool for selective pyrochemical processes based on molten salts in nuclear industry
Keywords: A0200; C0400; L0300; M0200; P0200; R0700; R1100;
Electrochemistry of nitrogen and nitrides in molten salts
Keywords: A0200; C0400; R1100; T0400;
Modelling thermal properties of actinide dioxide fuels
Keywords: A0200; F0700; M0200; P0700; T0500; T0600; T0700; U0200;
Kinetics of the actinides-lanthanides separation: mass transfer between molten fluorides and liquid metal at high temperatures
Keywords: A0200; C0400; K0100; R1100;