Keywords: حمل و نقل نوترون; Neutron transport; Self-shielding; Equivalence; Condensation; Discontinuity factors; Jump conditions;
مقالات ISI حمل و نقل نوترون (ترجمه نشده)
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Keywords: حمل و نقل نوترون; Neutron transport; Lattice Boltzmann method; Adaptive mesh refinement; Nuclear reactor;
Keywords: حمل و نقل نوترون; Method of Characteristics (MOC); Particle conservation; Neutron balance; Linear source; Neutron transport;
Keywords: حمل و نقل نوترون; Monte Carlo methods; Neutron transport; GPU; Monte Carlo volume ray-casting; MCATK; MonteRay;
Keywords: حمل و نقل نوترون; Neutron density; Neutron flux; Neutron source; Neutron transport; Monte Carlo codes; MCNP; 252Cf fission spectrum;
Keywords: حمل و نقل نوترون; Monte Carlo; Neutron transport; Parallelism; Vectorization;
Keywords: حمل و نقل نوترون; IGA; Neutron transport; Multigroup; Energy-dependent meshes;
Keywords: حمل و نقل نوترون; Goal-based; Error estimation; Diamond difference; Neutron transport; DWR; AMR;
Keywords: حمل و نقل نوترون; Method of characteristics; Neutron transport; Reactor simulation; High performance computing; Stochastic methods;
Keywords: حمل و نقل نوترون; odCMFD; CMFD; pCMFD; Neutron transport; Fourier analysis;
Keywords: حمل و نقل نوترون; Neutron transport; Transient; Reactivity initiated accident;
Keywords: حمل و نقل نوترون; Neutron transport; Time-eigenvalue(α); K-eigenvalue; Power iteration method;
Keywords: حمل و نقل نوترون; Radiative transfer; Neutron transport; Angular moments; Spatial moments; Case’s method; Chandrasekhar H-function
Keywords: حمل و نقل نوترون; Neutron transport; Nuclear fuel cell; Spectral elements; Transfinite interpolation
Keywords: حمل و نقل نوترون; Monte Carlo; Neutron transport; Reactor simulation; Cross section; Benchmarks; High performance computing;
Keywords: حمل و نقل نوترون; LWR multi-physics; Noise analysis; Neutron transport; Fluid dynamics; Heat transfer;
Keywords: حمل و نقل نوترون; Monte Carlo; Neutron transport; Coupled calculation; Feedback; Thermal-hydraulics
Keywords: حمل و نقل نوترون; Molten salt reactor; Neutron Transport; Fast reactor; Nuclear power; Nuclear reactor; Neutron shielding
Keywords: حمل و نقل نوترون; Neutron transport; Spectral elements; Reactor physics; Manufactured solutions
Keywords: حمل و نقل نوترون; Anderson Acceleration; Neutron transport; Plasma physics; Boltzmann equations
Keywords: حمل و نقل نوترون; Response matrix method; Reactor physics; Neutron transport; Eigenvalue solvers; Nonlinear solvers;
Keywords: حمل و نقل نوترون; Monte Carlo; Domain decomposition; Load balancing; Neutron transport; Nuclear reactor analyses;
Keywords: حمل و نقل نوترون; Neutron transport; Adaptivity; Goal-based adaptivity; A posteriori error analysis; Spherical harmonics
Keywords: حمل و نقل نوترون; Continuous energy; Monte Carlo; Neutron transport; Energy lookup; Optimization;
Fast solution of neutron transport SP3 equation by reduced basis finite element method
Keywords: حمل و نقل نوترون; Neutron transport; Reduced basis; Finite element method;
Discontinuous Galerkin spatial discretisation of the neutron transport equation with pyramid finite elements and a discrete ordinate (SN) angular approximation
Keywords: حمل و نقل نوترون; Neutron transport; Discontinuous Galerkin finite element; DGFEM; Pyramid; Discrete ordinates;
Gemma: Development of a two-dimensional neutron transport code with the method of characteristics
Keywords: حمل و نقل نوترون; Method of characteristics; Neutron transport; Criticality; Gemma code;
Enhanced geometric capabilities for the transient analysis code T-ReX and its application to simulating TREAT experiments
Keywords: حمل و نقل نوترون; Transient; IQS method; Neutron transport; Time dependent; TREAT; T-ReX;
An improved convergence rate for the prompt α eigenvalue calculation in α-k iteration methods
Keywords: حمل و نقل نوترون; Neutron transport; Prompt time- or α-eigenvalue; Monte Carlo method; α-k iteration method; Physical adjusting technique;
ARRC: A random ray neutron transport code for nuclear reactor simulation
Keywords: حمل و نقل نوترون; The Random Ray Method; Method of characteristics; Neutron transport; Reactor simulation; High performance computing;
Analysis of activation and damage of ITER material samples expected from DD/DT campaign at JET
Keywords: حمل و نقل نوترون; Jet; Neutron transport; Activation analysis; Functional materials;
Track truncation method for improving the computational efficiency of 2D matrix MOC
Keywords: حمل و نقل نوترون; Method of characteristics; Neutron transport; Preconditioned Krylov subspace technique; Track truncation method;
Performance and accuracy of criticality calculations performed using WARP - A framework for continuous energy Monte Carlo neutron transport in general 3D geometries on GPUs
Keywords: حمل و نقل نوترون; Monte Carlo; Neutron transport; GPU; CUDA; OptiX; Supercomputing;
Accurate reflective boundary condition in the PN method
Keywords: حمل و نقل نوترون; Reflective boundary condition; PN method; Spherical harmonics expansion; Neutron transport; Radiation transport;
On the calculation of angular neutron flux in MCNP
Keywords: حمل و نقل نوترون; Angular flux; Neutron flux; Neutron transport; Monte Carlo; MCNP; Computer code; Solid angle partitioning;
Neutron transport simulation in high speed moving media using Geant4
Keywords: حمل و نقل نوترون; Geant4; Neutron transport; Moving media;
Fourier analysis of iteration schemes for k-eigenvalue transport problems with flux-dependent cross sections
Keywords: حمل و نقل نوترون; Fourier analysis; Coupled physics; Neutron transport; Iterative convergence;
An adaptive, hanging-node, discontinuous isogeometric analysis method for the first-order form of the neutron transport equation with discrete ordinate (SN) angular discretisation
Keywords: حمل و نقل نوترون; Adaptive; Hanging-node; Isogeometric analysis; Hyperbolic equations; Neutron transport; Discrete ordinates;
Competing energy lookup algorithms in Monte Carlo neutron transport calculations and their optimization on CPU and Intel MIC architectures
Keywords: حمل و نقل نوترون; Monte Carlo; Neutron transport; Cross section; Table lookup; Intel MIC; Vectorization;
Activity inventories and decay heat calculations for a DEMO with HCPB and HCLL blanket modules
Keywords: حمل و نقل نوترون; DEMO; Neutron transport; Activation analysis; Structural materials;
3D/2D rotational plane slicing method for 3D whole-core transport calculation
Keywords: حمل و نقل نوترون; Method of characteristics; Neutron transport; 3D whole-core analysis;
DRAGON5 and DONJON5, the contribution of Ãcole Polytechnique de Montréal to the SALOME platform
Keywords: حمل و نقل نوترون; Lattice code; Neutron transport; Deterministic solution; Computational scheme; Computer-aided design;
A prestorage method to measure neutron transmission of ultracold neutron guides
Keywords: حمل و نقل نوترون; Ultracold neutron; Neutron transmission; Neutron transport; Neutron guide; Ultracold neutron source
Competing Energy Lookup Algorithms in Monte Carlo Neutron Transport Calculations and Their Optimization on CPU and Intel MIC Architectures
Keywords: حمل و نقل نوترون; Monte Carlo; neutron transport; cross section; table lookup; Intel MIC; vectorization
Optimized tracking strategies for step MOC calculations in extruded 3D axial geometries
Keywords: حمل و نقل نوترون; Neutron transport; MOC; 3D; Axial geometries;
Stability of Monte Carlo k-eigenvalue simulations with CMFD feedback
Keywords: حمل و نقل نوترون; Neutron transport; Hybrid methods; k-eigenvalue problems; Fourier analysis;
A task-based parallelism and vectorized approach to 3D Method of Characteristics (MOC) reactor simulation for high performance computing architectures
Keywords: حمل و نقل نوترون; Method of Characteristics; Neutron transport; Reactor simulation; High performance computing;
Implementation, capabilities, and benchmarking of Shift, a massively parallel Monte Carlo radiation transport code
Keywords: حمل و نقل نوترون; Monte Carlo methods; Neutron transport; Parallel computation;
Discontinuous isogeometric analysis methods for the first-order form of the neutron transport equation with discrete ordinate (SN) angular discretisation
Keywords: حمل و نقل نوترون; Isogeometric; Neutron transport; Hyperbolic equations; Discontinuous Galerkin; Discrete ordinates; Reactor physics;
Verification of ARES transport code system with TAKEDA benchmarks
Keywords: حمل و نقل نوترون; ARES; Critical calculation; Discrete ordinates; Neutron transport; TAKEDA benchmarks;