Keywords: فیزیک راکتور; Reactor physics; Generation IV; Super Critical Water Reactor; Few-group structure;
مقالات ISI فیزیک راکتور (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: فیزیک راکتور; Reactor physics; Resonance treatment; Resonance self-shielding; Equivalence theory; Light water reactor; Slowing-down;
Keywords: فیزیک راکتور; Serpent; Monte Carlo; Reactor physics; Homogenization; Burnup calculation;
Keywords: فیزیک راکتور; Reactor physics; Self-shielding; Lattice code; DRAGON5;
Keywords: فیزیک راکتور; Method of characteristics; Partial differential equations; Nuclear engineering; Reactor physics; Thermal hydraulics; AGENT;
Keywords: فیزیک راکتور; Nuclear engineering; Reactor physics; Neutron transport theory; Transport approximation; Anisotropic scattering; Lattice physics code; Light water reactor; Neutron leakage;
Keywords: فیزیک راکتور; Neutron transport; Spectral elements; Reactor physics; Manufactured solutions
Keywords: فیزیک راکتور; Response matrix method; Reactor physics; Neutron transport; Eigenvalue solvers; Nonlinear solvers;
Keywords: فیزیک راکتور; Reactor physics; Burnable poison; Small reactors; Reactivity coefficients
Development of a core design capability for innovative boiling water reactor designs for burning transuranic isotopes using WIMS/PANTHER
Keywords: فیزیک راکتور; Resource-renewable BWR; Reactor physics;
Core design and performance of the FASt TEst reactor (FASTER)
Keywords: فیزیک راکتور; Fast reactor; Test reactor; Neutronics; Reactor physics; Irradiation performance; Core design;
Verification of the HTR code package (HCP) as a comprehensive HTR steady state and transient safety analysis framework
Keywords: فیزیک راکتور; HTR; Simulation; Reactor Physics; Code Package; HCP;
Monte Carlo modeling and simulations of AHTR fuel assembly to support V&V of FHR core physics methods
Keywords: فیزیک راکتور; FHR; AHTR; V&V; Monte Carlo; SERPENT; Reactor physics;
Impact of new nuclear data on neutronic calculations of the OPAL Reactor using Serpent
Keywords: فیزیک راکتور; Reactor physics; Nuclear data; Cross sections; OPAL Reactor; Benchmark;
Introduction to Moltres: An application for simulation of Molten Salt Reactors
Keywords: فیزیک راکتور; Molten Salt Reactors; Multiphysics; Parallel computing; Finite elements; Reactor physics; MOOSE;
Core geometry for recriticality prevention against CDA in sodium-cooled fast reactor
Keywords: فیزیک راکتور; Sodium-cooled fast reactor; CDA; Recriticality prevention; Core geometry; Reactor physics;
MOCUM solutions and sensitivity study for C5G7 benchmark
Keywords: فیزیک راکتور; Method of characteristic; Reactor physics; Benchmark; C5G7; Parallel computing;
Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system
Keywords: فیزیک راکتور; Serpent; DYN3D; Monte Carlo; Reactor physics; Burnup; Research reactor
Discontinuous isogeometric analysis methods for the first-order form of the neutron transport equation with discrete ordinate (SN) angular discretisation
Keywords: فیزیک راکتور; Isogeometric; Neutron transport; Hyperbolic equations; Discontinuous Galerkin; Discrete ordinates; Reactor physics;
Recent developments of JAEA's Monte Carlo code MVP for reactor physics applications
Keywords: فیزیک راکتور; Monte carlo; MVP; Neutron/photon transport; Reactor physics; Reactor design; Criticality safety;
Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code
Keywords: فیزیک راکتور; High temperature reactor; Pebble bed reactor; Reactor physics; Monte Carlo; Discrete element method;
TRIGA reactor absolute neutron flux measurement using activated isotopes
Keywords: فیزیک راکتور; Neutron flux; Neutron activation; Monte Carlo; Reactor physics; Gamma-ray spectroscopy; Activation cross sections
Benchmarking of the WIMSD/CITATION deterministic code system for the neutronic calculations of TRIGA Mark-III research reactors
Keywords: فیزیک راکتور; Neutronic calculations; Reactor physics; TRIGA; WIMSD-5B; WIMSD-IAEA; TRX, BAPL benchmark lattices;
G4-STORK: A Geant4-based Monte Carlo reactor kinetics simulation code
Keywords: فیزیک راکتور; Monte Carlo; Reactor kinetics; Reactor physics; GEANT-4; Fission reactions; Neutron kinematics
Implementation of a direct perturbation method in MCNP and application to SCALE verification
Keywords: فیزیک راکتور; Sensitivity and uncertainty; Nuclear data; Reactor physics; Monte Carlo;
The MARVEL assembly for neutron multiplication
Keywords: فیزیک راکتور; Neutron multiplication; Reactor physics; Training
A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel
Keywords: فیزیک راکتور; Reactor Physics; Neutron detection; Measurement techniques; Research reactors; Burn-up
A response-based time-dependent neutron transport method
Keywords: فیزیک راکتور; Time-dependent transport theory; Response function; Reactor physics
Benchmark evaluation of reactor critical parameters and neutron fluxes distributions at zero power for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP
Keywords: فیزیک راکتور; TRIGA; Reactor physics; Monte Carlo; Neutron flux; Critical parameter
Status of HELIAS reactor studies
Keywords: فیزیک راکتور; Stellarator fusion reactor; Power plant; Blanket; Maintenance; Reactor physics