
Sweep3d
 Referenced in 6 articles
[sw12703]
 SWEEP3D: 3D Discrete Ordinates Neutron Transport. The benchmark code SWEEP3D represents the heart ... ordinates (Sn) 3D cartesian (XYZ) geometry neutron transport problem. The XYZ geometry is represented...

parafish
 Referenced in 3 articles
[sw18097]
 parafish: A parallel FE–PN neutron transport solver based on domain decomposition. A new core ... presented for the solution of large neutron transport core calculations. The secondorder evenparity...

AutoMOC
 Referenced in 2 articles
[sw36389]
 Auto MOC  A 2D neutron transport code for arbitrary geometry based on the method ... customization of AutoCAD. A new 2D neutron transport code AutoMOC for arbitrary geometry has been ... AutoCAD. The MOC solves the neutron transport equation along characteristic lines. It is independent ... used to solve the neutron transport equation in highly complex geometries. However, it is important...

Styx
 Referenced in 3 articles
[sw18343]
 used to solve the neutron transport problem. When only a small amount of information...

OpenMC
 Referenced in 11 articles
[sw18083]
 Monte Carlo particle transport simulation code focused on neutron criticality calculations. It is capable...

ntkfoam
 Referenced in 1 article
[sw36388]
 ntkfoam: an OpenFOAM based neutron transport kinetics solver for nuclear reactor simulation ... software OpenFOAM, this work establishes a neutron transport kinetics solver, namely ntkFoam, for the nuclear ... implementations. The coupling between multigroup neutron transport equations and the delayed neutron precursor balance ... calculated, and by coupling the neutron transport and delayed neutron precursor calculations using the Euler...

DYN3D
 Referenced in 2 articles
[sw19397]
 with multiple energy groups and SP3 neutron transport option is being developed...

Milne
 Referenced in 2 articles
[sw10765]
 classical Milne’s problem of neutron transport for the planar one speed and isotropic scattering...

Insilico
 Referenced in 2 articles
[sw18203]
 geometry, meshing, cross section processing, and neutron transport options. Numerical results demonstrate that Insilico using...

TORT
 Referenced in 1 article
[sw09083]
 Methodology to resolve the transport equation with the discrete ordinates code TORT into the IPEN/MB01 ... reactor Resolution of the steadystate Neutron Transport Equation in a nuclear pool reactor ... Discrete Ordinates method solves the Neutron Transport Equation for a set of selected directions, obtaining...

MonteRay
 Referenced in 1 article
[sw29212]
 acceleration of existing Monte Carlo particle transport codes as there is little modification ... volumetricraycasting estimator for neutron transport on GPU hardware in comparison to the standard ... estimator on CPU hardware. Evaluation of neutron transport through air in a criticality accident scenario...

TORTTD/ATTICA3D
 Referenced in 1 article
[sw07343]
 transient 3D transport coupled code TORTTD/ATTICA3D for highfidelity pebblebed HTGR ... power, the application of timedependent neutron transport methods becomes feasible for best estimate evaluations ... with focus on the timedependent neutron transport features of TORTTD. Results obtained...

ATTILA
 Referenced in 7 articles
[sw18120]
 been used for such applications. Existing deterministic transport codes were not applied to such problems ... interesting and challenging application of neutron and/or gammaray transport is nuclear welllogging applications...

Ardra
 Referenced in 1 article
[sw13224]
 Parallel Code System to Perform Neutron and Radiation Transport Calculations. Ardra offers robust scalable solution ... methods for neutron and radiation transport problems in complex 3D geometries. High resolution ... ability to model the transport of neutral particles (such as neutrons and photons) through matter ... parallel code system to perform neutral particle transport calculations in three dimensions...

CASMO
 Referenced in 10 articles
[sw18055]
 model” and the ability to perform 2D transport calculations in hundreds of energy groups. This ... neutron and 18 group gamma), and details recent work to validate CASMO5 2D transport...

MCNP
 Referenced in 34 articles
[sw07836]
 Particle Transport Code. Monte Carlo NParticle Transport Code (MCNP) is a software package ... capability to simulate particle interactions involving neutrons, photons, and electrons. ”Specific areas of application include...

ADVANTG
 Referenced in 1 article
[sw18292]
 fixedsource neutron, photon, and coupled neutronphoton transport problems using MCNP5 (X5 Monte...

MORSECGA
 Referenced in 1 article
[sw18301]
 MORSEEMP, MonteCarlo Neutron and Gamma MultiGroup Transport with Array Geometry, for PC. MORSE ... MORSE code is a multipurpose neutron and gammaray transport Monte Carlo code ... multigroup cross sections, the solution of neutron, gammaray, or coupled neutrongammaray problems...

RESTRAX
 Referenced in 0 articles
[sw22753]
 same time, physically realistic models for neutron transport through key neutron optical components like sources...

REACTOR
 Referenced in 2 articles
[sw02965]
 outer iterations convergence for the neutron and gammarays transport equation in onedimensional geometries ... weighted diamond differencing discrete ordinates multigroup transport equation in onedimensional geometries is discussed ... acceleration technique is described for anisotropic scattering neutron thermalization problems and subcritical fission boundary problems...