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Volume 141

Number 3

Neutron Spectrum Effects on Burnup, Reactivity, and Isotopics in UO2/H2O Lattices

Zhiwen Xu, Michael J. Driscoll, Mujid S. Kazimi

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 175-189

Technical Paper / dx.doi.org/10.13182/NSE02-A2277

Object-Oriented Three-Dimensional Fine-Mesh Transport Calculation on Parallel/Distributed Environments for Advanced Reactor Core Analyses

Masahiro Tatsumi, Akio Yamamoto

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 190-217

Technical Paper / dx.doi.org/10.13182/NSE02-A2278

A Variational Nodal Expansion Method for the Solution of Multigroup Neutron Diffusion Equations with Heterogeneous Nodes

Makoto Tsuiki, Sverre Hval

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 218-235

Technical Paper / dx.doi.org/10.13182/NSE02-A2279

Fully Consistent Diffusion Synthetic Acceleration of Linear Discontinuous SN Transport Discretizations on Unstructured Tetrahedral Meshes

James S. Warsa, Todd A. Wareing, Jim E. Morel

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 236-251

Technical Paper / dx.doi.org/10.13182/NSE141-236

The Evaluation of Radiation Transport Forward-Adjoint Flux Integrals Using Monte Carlo Correlated Coupling Methods

S. N. Cramer

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 252-271

Technical Paper / dx.doi.org/10.13182/NSE02-A2281

Cluster-Event Biasing in Monte Carlo Applications to Systems Reliability

Michael Khazen, Arie Dubi

Nuclear Science and Engineering / Volume 141 / Number 3 / July 2002 / Pages 272-287

Technical Paper / dx.doi.org/10.13182/NSE02-A2282

 
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