American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 155 / Number 2

Volume 155

Number 2

A Hybrid Monte Carlo-Deterministic Method for Global Particle Transport Calculations

Troy L. Becker, Allan B. Wollaber, Edward W. Larsen

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 155-167

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2653

A Lumped Linear-Discontinuous Spatial Discretization Scheme for Triangular-Mesh Sn Calculations in r-z Geometry

Jim E. Morel, Alejandro Gonzalez-Aller, James S. Warsa

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 168-178

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2654

An Efficient Exponential Directional Iterative Differencing Scheme for Three-Dimensional Sn Computations in XYZ Geometry

Glenn E. Sjoden

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 179-189

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2655

A Two-Dimensional Discontinuous Heterogeneous Finite Element Method for Neutron Transport Calculations

Emiliano Masiello, Richard Sanchez

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 190-207

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2656

A Nonlinear Space-Angle Multigrid Acceleration for the Method of Characteristics in Unstructured Meshes

Gabriele Grassi

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 208-222

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2657

An Integral Multidomain DPN Operator as Acceleration Tool for the Method of Characteristics in Unstructured Meshes

Simone Santandrea

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 223-235

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE155-223

Solving Three-Dimensional Large-Scale Neutron Transport Problems Using Hybrid Shared-Distributed Parallelism and Characteristics Method

Mohamed Dahmani, Robert Roy

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 236-249

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE155-236

MINOS: A Simplified Pn Solver for Core Calculation

Anne-Marie Baudron, Jean-Jacques Lautard

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 250-263

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2660

Component Mode Synthesis Methods for 3-D Heterogeneous Core Calculations Applied to the Mixed-Dual Finite Element Solver MINOS

Pierre Guérin, Anne-Marie Baudron, Jean-Jacques Lautard, Serge Van Criekingen

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 264-275

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2661

Neutron Transport Models of AEGIS: An Advanced Next-Generation Neutronics Design System

Naoki Sugimura, Akio Yamamoto, Tadashi Ushio, Masaaki Mori, Masato Tabuchi, Tomohiro Endo

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 276-289

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE155-276

A Quasilinear Implicit Riemann Solver for the Time-Dependent Pn Equations

Ryan G. McClarren, James Paul Holloway, Thomas A. Brunner, Thomas A. Mehlhorn

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 290-299

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2663

The Boundary Source Method with Arbitrary Order Anisotropic Scattering

Gert Van den Eynde, Robert Beauwens, Ernest Mund

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 300-309

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2664

A Review of Legacy and Advanced Self-Shielding Models for Lattice Calculations

Alain Hébert

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 310-320

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE06-50

Variational Estimates of Neutron-Induced Gamma Line Leakages and Ratios for Internal Interface Perturbations

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 155 / Number 2 / February 2007 / Pages 321-329

Technical Paper / Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications / dx.doi.org/10.13182/NSE07-A2666

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement