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Volume 155 / Number 2

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Table of Contents

Nuclear Science and Engineering / Volume 155 / Number 2

February 2007

Preface

Richard Sanchez

Nuclear Science and Engineering / Volume 155 / Number 2 / Page vii

February 2007

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 / Pages 155-167

February 2007

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Price:$30.00

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 / Pages 168-178

February 2007

Format:

Price:$30.00

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 / Pages 179-189

February 2007

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

Emiliano Masiello, Richard Sanchez

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

February 2007

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Price:$30.00

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

Gabriele Grassi

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

February 2007

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Price:$30.00

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 / Pages 223-235

February 2007

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Price:$30.00

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 / Pages 236-249

February 2007

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Price:$30.00

MINOS: A Simplified Pn Solver for Core Calculation

Anne-Marie Baudron, Jean-Jacques Lautard

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

February 2007

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Price:$30.00

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 / Pages 264-275

February 2007

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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 / Pages 276-289

February 2007

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Price:$30.00

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 / Pages 290-299

February 2007

Format:

Price:$30.00

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 / Pages 300-309

February 2007

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Price:$30.00

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

Alain Hébert

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

February 2007

Format:

Price:$30.00

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 / Pages 321-329

February 2007

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Price:$30.00
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