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Volume 147

Number 2

Super-Nodal Methods for Space-Time Kinetics

Ugur Mertyurek, Paul J. Turinsky

Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 93-126

Technical Paper

Convergence Analysis of the Nonlinear Coarse-Mesh Finite Difference Method for One-Dimensional Fixed-Source Neutron Diffusion Problem

Deokjung Lee, Thomas J. Downar, Yonghee Kim

Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 127-147

Technical Paper

Optimized Algorithm for Collision Probability Calculations in Cubic Geometry

R. D. M. Garcia

Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 148-157

Technical Paper

Singular Solutions, Integral Transport Theory, and the Sn Method

J. E. Morel, K. D. Lathrop

Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 158-166

Technical Paper

Neutron Flux Distribution in a Cavity with a Point Source

Biplab Ghosh, S. B. Degweker

Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 167-175

Technical Paper

Acceleration of Response Matrix Method Using Cross-Section Scaling

Akio Yamamoto

Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 176-184

Technical Paper

Evaluation of the Efficiency of Gamma Spectrometers for Measuring Volumetric Samples

Nader M. A. Mohamed, M. Abou Mandour

Nuclear Science and Engineering / Volume 147 / Number 2 / June 2004 / Pages 185-188

Technical Paper

 
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