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Volume 102

Number 2

Spin-Dependent Calculation of Fission Neutron Spectra and Fission Spectrum Integrals for Six Fissioning Systems

R. L. Walsh

Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 119-133

Technical Paper / dx.doi.org/10.13182/NSE89-A23637

Optimal Control of a Boiling Water Reactor Load-Following Operation

Chaung Lin, Zhih Pao Lin, Wern Jiahn Jiang

Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 134-139

Technical Paper / dx.doi.org/10.13182/NSE89-A23638

Interface Angular Coupling Reductions in Variational Nodal Methods for Neutron Transport

E. E. Lewis

Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 140-152

Technical Paper / dx.doi.org/10.13182/NSE89-A23639

A Simulation-Based Expert System for Nuclear Power Plant Diagnostics

Jeré A. Hassberger, John C. Lee

Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 153-171

Technical Paper / dx.doi.org/10.13182/NSE89-A23640

Time-Dependent Single-Collision Kernels for Integral Transport Theory

D. L. Henderson, C. W. Maynard

Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 172-182

Technical Paper / dx.doi.org/10.13182/NSE89-A23641

Boundary Condition Perturbation Theory for Use in Spatial Homogenization Methods

Farzad Rahnema

Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 183-190

Technical Paper / dx.doi.org/10.13182/NSE89-3

Empirical Formulas of Neutron Flux Distributions in Cylindrical Ducts in Water or Concrete Shields

Toshimasa Miura

Nuclear Science and Engineering / Volume 102 / Number 2 / June 1989 / Pages 191-209

Technical Paper / dx.doi.org/10.13182/NSE89-A23643