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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

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

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

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

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

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

 
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