Andere Kunden interessierten sich auch für
![Time Dependent Discrete Ordinates Neutron Transport Using Distribution Iteration in XYZ Geometry]( "Time Dependent Discrete Ordinates Neutron Transport Using Distribution Iteration in XYZ Geometry")
Time Dependent Discrete Ordinates Neutron Transport Using Distribution Iteration in XYZ Geometry59,99 €![Short and Independent Characteristic Methods for Discrete Ordinates Radiation Transport with 2D and 3D Regular Cartesian Meshes]( "Short and Independent Characteristic Methods for Discrete Ordinates Radiation Transport with 2D and 3D Regular Cartesian Meshes")
Short and Independent Characteristic Methods for Discrete Ordinates Radiation Transport with 2D and 3D Regular Cartesian Meshes59,99 €![Distribution Iteration: A Robust Alternative to Source Iteration for Solving the Discrete Ordinates Radiation Transport Equations in Slab and]( "Distribution Iteration: A Robust Alternative to Source Iteration for Solving the Discrete Ordinates Radiation Transport Equations in Slab and")
Distribution Iteration: A Robust Alternative to Source Iteration for Solving the Discrete Ordinates Radiation Transport Equations in Slab and59,99 €![The Development and Application of Reactive Transport Modeling Techniques to Study Radionuclide Migration at Yucca Mountain, NV]( "The Development and Application of Reactive Transport Modeling Techniques to Study Radionuclide Migration at Yucca Mountain, NV")
The Development and Application of Reactive Transport Modeling Techniques to Study Radionuclide Migration at Yucca Mountain, NV59,99 €![Investigation of Gate Current In Neutron Irradiated AlxGa1-xN/GaN Heterogeneous Field Effect Transistors Using Voltage and Temperature Dependence]( "Investigation of Gate Current In Neutron Irradiated AlxGa1-xN/GaN Heterogeneous Field Effect Transistors Using Voltage and Temperature Dependence")
Investigation of Gate Current In Neutron Irradiated AlxGa1-xN/GaN Heterogeneous Field Effect Transistors Using Voltage and Temperature Dependence59,99 €![Efficient and Accurate Computation of Non-Negative Anisotropic Group Scattering Cross Sections for Discrete Ordinates and Monte Carlo Radiaton Transpo]( "Efficient and Accurate Computation of Non-Negative Anisotropic Group Scattering Cross Sections for Discrete Ordinates and Monte Carlo Radiaton Transpo")
Efficient and Accurate Computation of Non-Negative Anisotropic Group Scattering Cross Sections for Discrete Ordinates and Monte Carlo Radiaton Transpo59,99 €![Improving Low Order, Linear, Positive Spatial Quadratures for the Partial Current Neutron Transport Method]( "Improving Low Order, Linear, Positive Spatial Quadratures for the Partial Current Neutron Transport Method")
Improving Low Order, Linear, Positive Spatial Quadratures for the Partial Current Neutron Transport Method59,99 €
A three-dimensional neutron transport based, heterogeneous reactor code (3D-TRAN) was developed to model simple uniform isotropic sources and isotropic fission sources. The code was developed using level symmetric angular quadrature sets and three spatial quadratures: the Diamond Difference (DD), Step, and Linear Characteristic (LC) methods. Each method was analyzed and compared for accuracy, rate of convergence, and stability. The LC method was found to be the most accurate method with a broader range of stability through heterogeneous absorbing regions than the DD method. The Step method always remains positive and stable, but converges very slowly to a specified answer in the limit as the mesh is refined.