Keywords: MCNP کد; Nuclear engine; Cylindrical geometry; Gaseous fuel; Critical in the gaseous state; Multiplication factor; MCNP code;
مقالات ISI MCNP کد (ترجمه نشده)
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Feasibility of 153Sm production using MNSR research reactor through a multi-stage approach
Keywords: MCNP کد; 153Sm production; MNSRs; Multi-stage approach; MCNP code;
Effect of a dual-purpose cask payload increment of spent fuel assemblies from VVER 1000 Bushehr Nuclear Power Plant on basket criticality
Keywords: MCNP کد; Dual-purpose Cask; VVER 1000 Spent Fuel; Criticality Safety; MCNP Code;
Calculation of the effects of Eu as impurity on the reactivity of the Miniature Neutron Source Reactors using the MCNP code
Keywords: MCNP کد; MNSR; MCNP code; Impurity; Europium; Beryllium reflector
Critical heavy water level and some parameters for the HWZPR reactor core using MCNP4c code
Keywords: MCNP کد; Benchmark calculations; Zero power reactor; MCNP code;
Thermoluminescence measurements of neutron streaming through JET Torus Hall ducts
Keywords: MCNP کد; JET Torus Hall; Neutron fluence; Neutron moderator; Thermoluminescence dosimetry; Lithium fluoride; MCNP code
Monte Carlo simulation of the BEGe detector response function for in vivo measurements of 241Am in the skull
Keywords: MCNP کد; In vivo measurements; 241Am; Internal contamination; BEGe detector; Monte Carlo calibrations; MCNP code
Nuclear heating and helium production at the inboard divertor rail for DEMO
Keywords: MCNP کد; DEMO; Neutronics; Monte Carlo simulations; MCNP code
Prediction of palladium-103 production using the Monte Carlo code MCNPX
Keywords: MCNP کد; Activity; MCNP code; Palladium-103; Rhodium target;
Analysis of different variance reduction techniques in research reactor beam tube calculations
Keywords: MCNP کد; Beam tube; MCNP code; Variance reduction; Neutron flux; Experimental facility; Design
Evaluation of collimators' response: Round and hexagonal holes in parallel and fan beam
Keywords: MCNP کد; Collimator; Geometry; Hexagonal; FWHM; Penetration; MCNP code
Monte Carlo simulation of pulse pile-up effect in gamma spectrum of a PGNAA system
Keywords: MCNP کد; Pile-up effect; Gamma spectrum; Monte Carlo simulation; MCNP code;
Development of a technique using MCNPX code for determination of nitrogen content of explosive materials using prompt gamma neutron activation analysis method
Keywords: MCNP کد; Prompt gamma neutron activation analysis; Explosive detection; Melamine; 252Cf source; Mass ratio of hydrogen to nitrogen; MCNP code;
Design of the thermal neutron beam for neutron radiography at the Syrian MNSR
Keywords: MCNP کد; Syrian MNSR; Neutron radiography; Thermal neutron; Photon filter; MCNP code;
Gamma self-shielding correction factors calculation for aqueous bulk sample analysis by PGNAA technique
Keywords: MCNP کد; Prompt gamma neutron activation analysis; Gamma self-shielding; Gamma mass attenuation; MCNP code; Unknown sample
Pulsed thermal neutron source at the fast neutron generator
Keywords: MCNP کد; Thermal neutrons; Time-decay constant; Pulsed neutron source; Monte Carlo simulations; MCNP code; Polyethylene
Gamma ray attenuation coefficient measurement for neutron-absorbent materials
Keywords: MCNP کد; Gamma ray attenuation coefficient; Neutron absorber; MCNP code; Xcom code
Detection limits of pollutants in water for PGNAA using Am–Be source
Keywords: MCNP کد; PGNAA; Am–Be source; Water pollution; MCNP code
The 4.438 MeV gamma to neutron ratio for the Am–Be neutron source
Keywords: MCNP کد; Am–Be neutron source; 4.438 MeV γγ-ray; Neutron emission rate; MCNP code
Use of MCNP code in energy dispersive X-ray fluorescence
Keywords: MCNP کد; 78.70.E; 02.70.LMonte Carlo simulation; MCNP code; X-ray fluorescence
Low-energy neutron flux measurement using a resonance absorption filter surrounding a lithium glass scintillator
Keywords: MCNP کد; 29.30.Hs; 29.40.McResonance absorption; Filter; Glass scintillators; MCNP code
Calculation of thermal neutron self-shielding correction factors for aqueous bulk sample prompt gamma neutron activation analysis using the MCNP code
Keywords: MCNP کد; 28.20.G; 28.20.F; 02.70.L; 82.80.JPrompt gamma neutron activation analysis; Neutron self-shielding; MCNP code
Study on the increase of inactive germanium layer in a high-purity germanium detector after a long time operation applying MCNP code
Keywords: MCNP کد; Inactive germanium layer; HPGe detector; MCNP code; γ Spectrometry; Detector efficiency
The investigation of Am–Be neutron source shield effect used on landmine detection
Keywords: MCNP کد; 25.40.Dn; 29.25.Dz; 28.20.CzLandmine; Am–Be source; MCNP code; BF3 detector; Polyethylene (PE); TNT
Radiation shield analyses in support of the FS design for the ITER ECRH launcher
Keywords: MCNP کد; ITER; Front Steering ECRH launcher; Neutronics; Monte Carlo method; MCNP code; McCad interface programme
Evaluation the nonlinear response function of a 3×3 in NaI scintillation detector for PGNAA applications
Keywords: MCNP کد; PGNAA; FWHM; GEB; NaI (Tl); MCNP code; Monte Carlo simulation; Nonlinear response; Neutron source; Response function; γ-ray component
Nuclear analysis of the copper alloys for fusion technologies by Monte Carlo method
Keywords: MCNP کد; Monte Carlo simulation; Positron annihilation spectroscopy; Neutronic calculation; Neutron irradiation; Defect production; MCNP code
Modelling of the non-stationary thermal neutron transport in hydrogenous media using the MCNP code
Keywords: MCNP کد; 24.10.Lx; 28.20.Gd; 28.20.Cz; 28.20.Fc; Monte Carlo simulations; MCNP code; Thermal neutron flux; Hydrogenous system; Scattering cross-section;
Monte Carlo simulation of intrinsic count rate performance of a scintillation camera for diagnostic images
Keywords: MCNP کد; Count rate performance; Monte Carlo simulation; Pile-up effect; MCNP code;
Application of imaging plate technique for separate detection of 3H and 14C
Keywords: MCNP کد; Tritium; Carbon-14; Imaging plate technique; MCNP code
Decay of the pulsed thermal neutron flux in two-zone hydrogenous systems - Monte Carlo simulations using MCNP standard data libraries
Keywords: MCNP کد; 28.20.Gd; 28.20.Cz; 28.20.Fc; Monte Carlo simulations; MCNP code; Pulsed thermal neutron flux; Hydrogenous system; Scattering cross-section;
Monte Carlo simulations of the pulsed thermal neutron flux in two-zone systems with Plexiglas - Using the MCNP code with a modified hydrogen-data library
Keywords: MCNP کد; 28.20.âv; 28.20.Gd; 28.20.Cz; 28.20.Fc; 24.10.Lx; Pulsed thermal neutron flux; Scattering cross-section; Hydrogenous material; Plexiglas; Monte Carlo simulations; MCNP code;
Tally modifying of MCNP and post processing of pile-up simulation with time convolution method in PGNAA
Keywords: MCNP کد; Time convolution; MCNP code; PGNAA; TALLYX subroutine; Pile-up; Gamma spectra; NaI(Tl) detector;