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Volume 155

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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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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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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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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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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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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

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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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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

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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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Description of the LANCER02 Lattice Physics Code for Single-Assembly and Multibundle Analysis

Dave Knott, Erin Wehlage

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 331-354

March 2007

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An Analysis of the Extended-Transport Correction with Application to Electron Beam Transport

Clifton R. Drumm, Wesley C. Fan, Leonard Lorence, Jennifer Liscum-Powell

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 355-366

March 2007

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Development of a Scatter Search Optimization Algorithm for Boiling Water Reactor Fuel Lattice Design

Juan-Luis François, Cecilia Martín-del-Campo, Luis B. Morales, Miguel-Angel Palomera

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 367-377

March 2007

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Coupled Bundle-Core Design Using Fuel Rod Optimization for Boiling Water Reactors

Matthew A. Jessee, David J. Kropaczek

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 378-385

March 2007

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Optimized Adaptive Fuzzy Controller of the Water Level of a Pressurized Water Reactor Steam Generator

M. Marseguerra, E. Zio, F. Cadini

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 386-394

March 2007

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High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor

David P. Weber, Tanju Sofu, Won Sik Yang, Thomas J. Downar, Justin W. Thomas, Zhaopeng Zhong, Jin Young Cho, Kang Seog Kim, Tae Hyun Chun, Han Gyu Joo, Chang Hyo Kim

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 395-408

March 2007

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Use of 3D-VAR and Kalman Filter Approaches for Neutronic State and Parameter Estimation in Nuclear Reactors

Sébastien Massart, Samuel Buis, Patrick Erhard, Guillaume Gacon

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 409-424

March 2007

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Theory of Neutron Noise in a Temporally Fluctuating Multiplying Medium

Lénárd Pál, Imre Pázsit

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 425-440

March 2007

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Atomic Mix Synthetic Acceleration of Dose Computations in Binary Statistical Media

Anil K. Prinja, Erin D. Fichtl

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 441-448

March 2007

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Investigation of the Impact of Simple Carbon Interstitial Formations on Thermal Neutron Scattering in Graphite

Ayman I. Hawari, Iyad I. Al-Qasir, Abderrafi M. Ougouag

Nuclear Science and Engineering / Volume 155 / Number 3 / Pages 449-462

March 2007

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