A Rayleigh Quotient Method For Criticality Eigenvalue Problems In Neutron Transport
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Nuclear science and engineering↗
Engineering topics
Bailey, T S
Publications and source records attributed to Bailey, T S.
TESTING OF ENDF/B-VIII.0 IN THE GNDS FORMAT WITH LLNL TRANSPORT CODES
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Physics - Nuclear physics and radiation physics↗
An Efficient Sweep-based Solver for the Sn Equations on High-Order Meshes
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Nuclear science and engineering, Mathematics and C↗
IMPLEMENTATION OF THE GNDS FORMAT FOR EVALUATED AND PROCESSED NUCLEAR DATA
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
A Rayleigh Quotient Method for Solving the Alpha-Eigenvalue Problem in Neutron Transport
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
A Rayleigh Quotient Method for Solving the Alpha-Eigenvalue Problem in Neutron Transport
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Locally-Refined Angular Quadrature Comparisons in Ardra
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
The Improved Simple Corner Balance Method and Efforts to Enhance its Computational Performance
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
KRIPKE - A MASSIVELY PARALLEL TRANSPORT MINI-APP
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Validation of Full-Domain Massively Parallel Transport Sweep Algorithms
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Provably Optimal Parallel Transport Sweeps on Regular Grids
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Thick Diffusion Limit Boundary Layer Test Problems
Abstract not provided
22 GENERAL STUDIES OF NUCLEAR REACTORS↗