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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

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

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

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

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

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

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

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

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

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

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

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

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

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

 
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