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Volume 120

Number 3

A Diffusion-Synthetic Acceleration Technique for the Even-Parity Sn Equations with Anisotropic Scattering

J. E. Morel, J. M. McGhee

Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 147-164

Technical Paper / dx.doi.org/10.13182/NSE95-A24116

Exponential Characteristic Spatial Quadrature for Discrete Ordinates Radiation Transport with Rectangular Cells

Bryan Minor, Kirk Mathews

Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 165-186

Technical Paper / dx.doi.org/10.13182/NSE95-A24117

Anisotropic Scattering Treatment for the Neutron Transport Equation with Primal Finite Elements

B. Akherraz, C. Fedon-Magnaud, J. J. Lautard, R. Sanchez

Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 187-198

Technical Paper / dx.doi.org/10.13182/NSE95-A24118

Effects of Linear Polarization and Doppler Broadening on the Exposure Buildup Factors of Low-Energy Gamma Rays

Y. Namito, S. Ban, H. Hirayama

Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 199-210

Technical Paper / dx.doi.org/10.13182/NSE95-A24119

Approximating Model for Multilayer Gamma-Ray Buildup Factors by Transmission Matrix Method: Application to Point Isotropic Source Geometry

Kazuo Shin, Hideo Hirayama

Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 211-222

Technical Paper / dx.doi.org/10.13182/NSE95-A24120

Neutron Temperature Measurements in a Cryogenic Hydrogenous Moderator

Russell M. Ball, Gary S. Hoovler, Robert H. Lewis

Nuclear Science and Engineering / Volume 120 / Number 3 / July 1995 / Pages 223-230

Technical Paper / dx.doi.org/10.13182/NSE95-A24121