Keywords: Neutron radiography; MCNPX; Electron linac; Thermal neutrons; Sapphire filter;
مقالات ISI (ترجمه نشده)
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Keywords: Positron annihilation; Positron sources; Positron stopping; Emission of positrons; Doppler broadening spectroscopy; 44Ti; Ion implantation; Spallation targets; Irradiation effects in solids; MCNPX;
Keywords: External source; MCNPX; TRU; ADSR; Fusion hybrid; Transmutation;
Keywords: Gamma spectroscopy; Self-absorption; MCNPX; LabSOCS;
Keywords: Linac; New corrected model; Photoneutron; Energy spectrum; Dose; MCNPX;
Keywords: Bremsstrahlung; electron linac; MCNPX; photoneutrons;
Keywords: Extensive air shower modeling; South Atlantic Magnetic Anomaly; Flight altitude; Monte Carlo method simulation; Geant4; MCNPX;
Keywords: Gamma beam - 127; Panoramic irradiator; Dose rate; MCNPX; Gamma irradiation facility;
Keywords: Homeland security; Radioactive dispersal device; Neutron techniques; Differential die away time analysis; Neutron generator; MCNPX;
Keywords: Ambient dose equivalent; Effective dose equivalent; Secondary neutron; Suborbital altitude; Low Earth orbit; Galactic cosmic radiation; MCNPX;
Keywords: Logical detector; Markus chamber; Proton therapy; MCNPX
Keywords: In situ gamma spectroscopy; Marine environment; NaI(Tl) detector; Efficiency calibration; MCNPX;
Keywords: Silicon photomultiplier (SiPM); Bluetooth; Mcnpx;
Keywords: MCNPX; Neutron radiography; Optimization; Neutron imaging parameters;
Keywords: SMR; CAREM25; MCNPX; Neutronic; Simulation; Flux;
Keywords: MCNPX; Neutrons; Gamma rays; Explosives; Dose;
Keywords: Fixed gamma ray detection system; Gamma dose equivalent; MCNPX; Tehran Research Reactor; Beam tube; TLD;
Keywords: Semiconductor radiation detectors; Photon dosimetry; Mammography; MCNPX;
Keywords: Nanofluid; Neutronic study; Corrosion and economic analysis; MCNPX
Keywords: Manganese Bath System (MBS); Compton-suppression; Neutron; MCNPX; Scintillator
Keywords: Resonance interference effect; Subgroup method; Neutron self-shielding; Interference correction factors; nTRACER code; MCNPX;
Keywords: Fusion-fission hybrid reactor; High level radioactive waste transmutation; Coolant options; MCNPX; Molten salt coolant; Transmutation performance;
Keywords: MCNPX; Suborbital; Space tourism; Neutron ambient dose equivalent; Neutron effective dose equivalent;
Keywords: LVR-15; Burnup measurement assembly; 110mAg; IRT-2M; MCNPX
Keywords: Free release measurement; Low activity measurement; Monte Carlo simulation; MCNPX; PENELOPE
Keywords: Liquid-jet anode; Monte Carlo simulation; Electron-impact ionization; MCNPX; PENELOPE; EGS5
Keywords: MCNPX; Traveling wave reactor; Flux profile
Keywords: Gamma spectrometry; Research reactor; Fuel pin; Fission products; MCNPX;
Keywords: Effective delayed neutron fraction; Adjoint flux; Monte Carlo; MCNPX
Keywords: CR-39; SSNTD; Accelerator Driven System (ADS); Graphite moderator; Spallation neutrons; MCNPX
Keywords: Broad energy germanium detector; Gamma-ray spectrometry; MCNPX; ISOCS; Collimator algorithms; Active area;
Keywords: VHTR; GT-MHR; MCNPX; Radioactive graphite; Neutronic analysis;
Keywords: Bi-spectral; Moderators; Optimization; MCNPX; ESS;
Keywords: Light water reactor fuel; Burnt fuel; Fission rates; Zero-power reactor; Gamma-ray spectrometry; Short-lived fission products; MCNPX;
Keywords: BNCT; Photo-neutron source; Antimony; MCNPX; Snyder head phantom
Keywords: Cold neutron; Modeling; Design; MCNPX; Tehran Research Reactor
Keywords: Distillation column; Gamma-ray CT; Structural inspection; MCNPX; Image reconstruction
Viability of uranium nitride (UN) as annular fuel for AP-1000
Keywords: Uranium nitride; Annular fuel; MCNPX; AP1000;
Investigation of photon shielding performances of some selected alloys by experimental data, theoretical and MCNPX code in the energy range of 81â¯keV-1333â¯keV
Keywords: Alloy; Shielding; MCNPX; Photon; Mass attenuation coefficients;
Evaluation of an alternative shielding materials for F-127 transport package
Keywords: F-127 transport packaging; Gamma shielding materials; MCNPX;
Neutronic design study of accelerator driven system (ADS) for Jordan subcritical reactor as a neutron source for nuclear research
Keywords: Proton; Spallation source; ADS; Subcritical; Neutron; MCNPX;
Monte Carlo calculation and verification of the geometrical factors for the NPDGamma experiment
Keywords: Monte Carlo; MCNPX; NPDGamma experiment;
Transmutation performance of uniform and nonuniform distributions of plutonium and minor actinides in TRIGA Mark II ADS reactor
Keywords: ADS; TRIGA Mark II; MCNPX; Plutonium; Minor actinides; Burnup; Mass ratio;
Reducing the plutonium stockpile around the world using a new design of VVER-1200 assembly
Keywords: VVER-1200; rgPu; wgPu; MCNPX; MTC; Fission products;
Comparison of different target material options for the European Spallation Source based on certain aspects related to the final disposal
Keywords: Radiation protection; Final disposal; Activation; Target material; Waste index; Clearance level; spallation source; Radioactive waste; MCNPX; CINDER;
Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code
Keywords: Thorium; Fast reactor; GCFR; Pu; Minor actinides; MCNPX;
FreeCAD based modeling study on MCNPX for accelerator driven system
Keywords: FreeCAD; MCNPX; ADS; Hierarchical tree; Ray-casting technology; Markov chain;
Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility
Keywords: Cold Neutron Source; MCNPX; Neutron Guides; Shield Design;
Assessment and estimation of 65Zn production yield via neutron induced reaction on natZnO and natZnONPs
Keywords: 65Zn; Production yield; MCNPX; TALYS; Thermal neutron;
Shielding features of concrete types containing sepiolite mineral: Comprehensive study on experimental, XCOM and MCNPX results
Keywords: Sepiolite; Radiation shielding; Attenuation coefficients; MCNPX; XCOM;