• 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 second-order even-parity...
  • 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 multi-group 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/MB-01 ... reactor Resolution of the steady-state 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 ... volumetric-ray-casting 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...
  • TORT-TD/ATTICA3D

  • Referenced in 1 article [sw07343]
  • transient 3-D transport coupled code TORT-TD/ATTICA3D for high-fidelity pebble-bed HTGR ... power, the application of time-dependent neutron transport methods becomes feasible for best estimate evaluations ... with focus on the time-dependent neutron transport features of TORT-TD. 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 gamma-ray transport is nuclear well-logging 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 3-D 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 CASMO-5 2D transport...
  • MCNP

  • Referenced in 34 articles [sw07836]
  • Particle Transport Code. Monte Carlo N-Particle 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]
  • fixed-source neutron, photon, and coupled neutron-photon transport problems using MCNP5 (X-5 Monte...
  • MORSE-CGA

  • Referenced in 1 article [sw18301]
  • MORSE-EMP, Monte-Carlo Neutron and Gamma MultiGroup Transport with Array Geometry, for PC. MORSE ... MORSE code is a multipurpose neutron and gamma-ray transport Monte Carlo code ... multigroup cross sections, the solution of neutron, gamma-ray, or coupled neutron-gamma-ray 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 gamma-rays transport equation in one-dimensional geometries ... weighted diamond differencing discrete ordinates multigroup transport equation in one-dimensional geometries is discussed ... acceleration technique is described for anisotropic scattering neutron thermalization problems and subcritical fission boundary problems...