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Volume 97

Number 3

Conceptual Design and Neutronics Analyses of a Fusion Reactor Blanket Simulation Facility

D. E. Beller, K. O. Ott, W. K. Terry

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 175-189

Technical Paper / dx.doi.org/10.13182/NSE87-A23500

Singular Perturbation Analysis of Limit Cycle Behavior in Nuclear-Coupled Density-Wave Oscillations

Mary E. Ward, John C. Lee

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 190-202

Technical Paper / dx.doi.org/10.13182/NSE87-A23501

Time-Dependent First-Flight Leakage Rates for Slabs, Spherical Shells, and Spheres

D. L. Henderson, C. W. Maynard

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 203-210

Technical Paper / dx.doi.org/10.13182/NSE97-203

Kinetics of Filtration of Model Crud with Ion Exchange Resin Bed

Masanori Takahashi, Kenkichi Ishigure, Norihiko Fujita

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 211-219

Technical Paper / dx.doi.org/10.13182/NSE87-A23503

Measurement and Analysis of an Angular Neutron Flux on a Beryllium Slab Irradiated with Deuterium-Tritium Neutrons

Yukio Oyama, Hiroshi Maekawa

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 220-234

Technical Paper / dx.doi.org/10.13182/NSE87-A23504

Ratio of the Prompt Fission Neutron Spectrum of 239Pu to That of 235U

Masayoshi Sugimoto, Alan B. Smith, Peter T. Guenther

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 235-238

Technical Note / dx.doi.org/10.13182/NSE87-A23505

Neutron Capture Cross Sections of Rhenium from 3 to 1900 keV

R. L. Macklin, P. G. Young

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 239-244

Technical Note / dx.doi.org/10.13182/NSE87-A23506

Implementation of Stratified Sampling for Monte Carlo Applications

Robert S. Brown, Jr., John S. Hendricks

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 245-248

Technical Note / dx.doi.org/10.13182/NSE87-A23507

Coarse-Mesh Diffusion Acceleration Technique for Transport Calculations

Vinicius-Nicolae-Petre Anghel

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 249-256

Technical Note / dx.doi.org/10.13182/NSE87-A23508