Keywords: نوترونیک; Small Modular Reactor; Thorium; Neutronic; SMART; MCNP;
مقالات ISI نوترونیک (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.
Keywords: نوترونیک; Fuel cladding; Nuclear reactor; EPR; Neutronic; Accident tolerant fuel;
Keywords: نوترونیک; SMR; CAREM25; MCNPX; Neutronic; Simulation; Flux;
Neutronic design optimization of ITER TBM port#2 bio-shield plug
Keywords: نوترونیک; Bio-shield; Neutronic; ITER; TBM port; Ferro-boron;
The application of nodal method for dynamic analysis of TRIGA Mark II
Keywords: نوترونیک; Dynamic analysis; Neutronic; Nodal method; Point kinetic; Thermal hydraulic; TRIGA;
Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square fuel assemblies using MCNP and CFX
Keywords: نوترونیک; SMR; Neutronic; Thermal hydraulic; MCNPX; CFX; CAREM25;
ERSN-OpenMC, a Java-based GUI for OpenMC Monte Carlo code
Keywords: نوترونیک; Neutronic; Monte Carlo; k-Eigenvalue criticality; OpenMC; Java; GUI
Verification of MCNP6 model of the Jordan Research and Training Reactor (JRTR) for calculations of neutronic parameters
Keywords: نوترونیک; JRTR; Neutronic; Keff; Criticality; Flux; Monte Carlo; Research reactor; Power peaking factor; MCNP6;
A novel multi objective Loading Pattern Optimization by Gravitational Search Algorithm (GSA) for WWER1000 core
Keywords: نوترونیک; Loading Pattern Optimization; Gravitational Search Algorithm; Neutronic; Thermal-hydraulic; WWER1000; PARCS; COBRA-EN;
Depletion calculations based on perturbations. Application to the study of a REP-like assembly at beginning of cycle with TRIPOLI-4®
Keywords: نوترونیک; Neutronic; Monte-Carlo simulation; Burnup/depletion calculation; Perturbation; Correlated sampling method; TRIPOLI-4®;
Thermal-hydraulic and neutronic experimental research in the TRIGA reactor of Brazil
Keywords: نوترونیک; Thermal-hydraulic; Neutronic; TRIGA reactor; Temperature; Reactivity;
Neutronic analysis of HPLWR fuel assembly cluster
Keywords: نوترونیک; Neutronic; HPLWR; Supercritical-pressure; Fuel assembly
Optimal design of measurement network for neutronic activity field reconstruction by data assimilation
Keywords: نوترونیک; Data assimilation; Neutronic; Activities reconstruction; Nuclear in-core measurements; Inverse problem; Network design; Simulated annealing; Metropolis-Hastings;
Two safety coefficients for a typical 13 × 13 annular fuel assembly
Keywords: نوترونیک; Annular fuel; MCNP -5; PWR; Simulation; Neutronic; Criticality
Performance evaluation/analysis of Pakistan Research Reactor-1 (PARR-1) current core configuration
Keywords: نوترونیک; Neutronic; Thermal hydraulic; PARR-1
Differential influence of instruments in nuclear core activity evaluation by data assimilation
Keywords: نوترونیک; Data assimilation; Neutronic; Activities reconstruction; Nuclear in-core measurements; Data acquisition network
The thorium molten salt reactor: Moving on from the MSBR
Keywords: نوترونیک; Molten salt reactor; Thorium cycle; Generation IV; Neutronic; Feedback coefficient; Breeding
Simulation of the VVER-1000 pump start-up experiment in the OECD/DOE/CEA V1000CT benchmark by the FLICA4/CRONOS2 coupled code system
Keywords: نوترونیک; VVER; Benchmark; Pump start-up; Code coupling; Neutronic; Thermal–hydraulic