Keywords: Space nuclear power; GPHS-RTG; NBDEx; MCNP; Monterburn; Nuclear battery
مقالات ISI (ترجمه نشده)
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Keywords: Artificial neural network; Gamma-ray attenuation; MCNP; Multiphase flow-prediction;
Keywords: Criticality; Dose rate; MCNP; ORIGEN; REBUS; WIMS
Keywords: BNCT; Lung tumours; Tumour control probability; MCNP
Keywords: Neutronic codes; Monte Carlo codes; Deterministic codes; MCNP; TRIPOLI; XSDRN;
Keywords: Microtron; Photoneutron; Beryllium; MCNP; EGS4; REM detector;
Keywords: Radiation shielding; Composite; Attenuation parameters; Removal cross-section; Physical properties; MCNP;
Keywords: Depletion analysis; Control absorber; Small research reactor; MCNP; Reactivity loss; ORIGEN-S;
Keywords: X-ray; Radiography; MCNP; Neutron imaging; Gamma imaging; Simulation;
Keywords: Ionization chamber; Fission chamber; MCNP; Material testing reactor; Nuclear heating;
Keywords: Rossi; Feynman; Ads; YALINA; MCNP; Subcritical;
Keywords: Fusion neutronics; Monte-Carlo; Multi-group; Unionised energy-grid; MCNP; Reaction rate;
Keywords: 14Â MeV neutron; Pulse propagation; Neutron waves; 90% Enriched uranium; Monte Carlo methods; MCNP;
Keywords: Sodium core; Thermal-hydraulics; Neutronics; MCNP; COBRA;
Keywords: Lithium orthosilicate; Tritium; TRR; MCNP
Keywords: Energy; Nuclear; Subcritical assembly; MCNP
Keywords: Nuclear data pre-processing; MCNP; Nuclear fusion
Physics study of liquid hydrogen moderator of CMRR reactor cold neutron source
Keywords: Cold moderator; Liquid hydrogen; Reactor neutron source; MCNP; Optimization;
Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT
Keywords: In-pile instrumentation; Irradiation environment; MCNP; Nuclear testing; Reactor characterization; Transient testing;
An online method to measure tritium production rate of fusion-fission hybrid reactor in CAEP
Keywords: 28.20.-v; 28.41.Ak; 28.52.Av; Fusion-fission hybrid reactor; Blanket benchmark mockups; Tritium production rate; MCNP;
The viability of ADVANTG deterministic method for synthetic radiography generation
Keywords: ADVANTG; MCNP; Deterministic; Radiography; CT; Imaging; Simulation; X-ray;
Measurement and analysis of 232Th(n,2n)231Th reaction rate in the thorium oxide cylinder with a D-T neutron source
Keywords: 232Th(n,2n) reaction rate; Neutron integral experiment; MCNP; D-T neutron source;
Reduction of the uncertainty due to fissile clusters in radioactive waste characterization with the Differential Die-away Technique
Keywords: Differential Die-away Technique; Matrix effect correction; Radioactive waste; MCNP; He3 detector; Fissile cluster;
Estimation of nuclear heating by delayed gamma rays from radioactive structural materials of HANARO
Keywords: Delayed Gamma-ray; HANARO; MCNP; Nuclear Heating; Neutron Irradiation; ORIGEN; Reactor Structure;
Neutronics analysis of the ITER Collective Thomson Scattering system
Keywords: ITER; Collective Thomson Scattering; Neutronics; Flux; Nuclear heat loads; MCNP; CTS;
Verification of SuperMC for MNSRs core analysis: The case of Ghana Research Reactor-I
Keywords: Modeling; Neutronics; SuperMC; Criticality; MCNP; MNSR-GHARR-1; Verification;
Two-way multi-physics coupling for modeling high power RbCl isotope production targets
Keywords: RbCl targetry; Thermal modeling; Multi-physics coupling; Isotope production; ANSYS; MCNP; High power targetry;
Using MCNP for success criteria evaluation of reactor trip function in probabilistic modeling of ATWS upon LOOP
Keywords: Success criteria; MCNP; Reactor trip; ATWS; PSA;
Study on collimator design for Neutron Science Facility of RAON accelerator complex
Keywords: Heavy ion accelerator; Neutron time of flight; Neutron collimator; MCNP;
Neutron shielding assessment for the Remote Handling Lower Port rack of ITER
Keywords: ITER; Remote Handling - Lower Port Rack; Neutronics; Shielding; MCNP;
Estimation of the dose rate of nuclear fuel of Ghana Research Reactor-1 (GHARR-1) using ORIGEN-S and MCNP 6
Keywords: Criticality; Dose rate; Source term; MCNP; ORIGEN-S;
An optimized epithermal BNCT beam design for research reactors
Keywords: BNCT; Epithermal neutron beam; Spectrum shifter; Research reactor; MCNP; Design optimization;
Analysis of VENUS-2 benchmark using Serpent 2 code
Keywords: VENUS-2; Serpent; MCNP; Monte Carlo; Full core calculations; MOX; Benchmark;
Computational validation of the fission rate distribution experimental benchmark at the JSI TRIGA Mark II research reactor using the Monte Carlo method
Keywords: TRIGA reactor; Miniature fission chamber; Absolute fission rate; Monte Carlo calculations; Uncertainty analysis; MCNP;
Thermal and epithermal neutron flux distributions measurement in thermal column of TRR using an experimental-simulation method
Keywords: Flux distributions; Thermal column; Epithermal neutron; Foil activation; MCNP;
Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations
Keywords: BEPU; best estimate plus uncertainty; CASL; consortium for advanced simulation of light water reactors; CIPS; crud induced power shift; CD-A; core design automation; CD-O; core design optimization; COBRA-TF; coolant-boiling in rod arrays-two fluids; FOM;
Validation and evaluation of the ADVANTG hybrid code on the ICSBEP labyrinth benchmark experiment
Keywords: ADVANTG; MCNP; Variance reduction;
Excitation functions for (p,x) reactions of niobium in the energy range of Epâ¯=â¯40-90â¯MeV
Keywords: Nbâ¯+â¯p; Cuâ¯+â¯p; Niobium; 90Mo; Nuclear cross sections; Stacked target activation; Monitor reactions; Medical isotope production; Isomer branching ratios; MCNP; LANL;
Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers
Keywords: TRIGA research reactor; Fission chamber; MCNP; Multiple in-core detectors; Control rod movement; Neutron flux redistribution;
PHITS Benchmarking for HPGe Detector Efficiency
Keywords: PHITS; benchmark; HPGe; efficiency; Cyltran; MCNP;
Feasibility of employing thick microbeams from superficial and orthovoltage kVp x-ray tubes for radiotherapy of superficial cancers
Keywords: Microbeam radiation therapy; Kilovoltage x-ray tube; Monte Carlo simulations; MCNP; Gafchromic EBT film; Parallel grid;
Statistical error propagation in HTR burnup model
Keywords: BPR; Burnable Poison Rod; BWR; Boiling Water Reactor; EFPD; Equivalent Full Power Days; HTR; High Temperature Reactor; keff; effective neutron multiplication factor; MC; Monte Carlo; MCB; continuous energy Monte Carlo burnup (code); MCNP; Monte Carlo N-Pa
Calculations to support JET neutron yield calibration: Modelling of neutron emission from a compact DT neutron generator
Keywords: Compact DT neutron generator; MCNP; Modelling;
Peak-to-valley ratios for three different HPGe detectors for the assessment of 137Cs deposition on the ground and the impact of the detector field-of-view
Keywords: Depth distribution; MCNP; PTV ratio; In situ; Field of view; Deposition; Cs-137; HPGe;
Simulation of the GCR spectrum in the Mars curiosity rover's RAD detector using MCNP6
Keywords: Space radiation; GCR; MCNP; RAD; MSL; Mars;
Delta-ray Production in MCNP 6.2.0
Keywords: MCNP; MCNP 6.2.0; delta-ray production; radiation transport;
Verification of Plutonium Content in PuBe Sources Using MCNP® 6.2.0 Beta with TENDL 2012 Libraries
Keywords: MCNP; (α,n); PuBe; isotopic composition; neutron yield;
Nuclear analyses of neutron activation system for Indian TBM
Keywords: Nuclear responses; LLCB TBM; NAS; Activation; MCNP;
An approach to design a 90Sr radioisotope thermoelectric generator using analytical and Monte Carlo methods with ANSYS, COMSOL, and MCNP
Keywords: Radioisotope thermoelectric generator; 90Sr; COMSOL; ANSYS; MCNP; Thermoelectric;
The effect of α-irradiation from enriched uranium on the leaching properties of PTFE
Keywords: MCNP; Polytetrafluoroethylene; Dose rate; Degradation; Enriched uranium; α-irradiation;