Volume 57
Number 3
- Table of Contents
- Comments on Variational Theory and Generalized Perturbation Methods
- Response to “Comments on Variational Theory and Generalized Perturbation Methods”
- Variational Versus Generalized Perturbation Theories—Are They Different
- The Streaming Term of the Transport Equation in Terms of General Orthogonal Coordinates
- A Benchmark Experiment of Neutron Propagation in Iron Used to Test ENDF/B Cross-Section Data
Generalized Continuous Neutron Slowing-Down Theory
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 179-187
Technical Paper / dx.doi.org/10.13182/NSE75-A26749
Elliptical Toroidal Geometry—A Geometric Transport Correction
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 188-195
Technical Paper / dx.doi.org/10.13182/NSE75-A26750
Energy-Dependent Applications of the Transfer Matrix Method
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 196-204
Technical Paper / dx.doi.org/10.13182/NSE75-A26751
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 205-217
Technical Paper / dx.doi.org/10.13182/NSE75-A26752
A Method of Monte Carlo Fitting
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 218-221
Technical Note / dx.doi.org/10.13182/NSE75-A26753
An Analysis of Selected Fast Critical Assemblies Using ENDF/B-IV Neutron Cross Sections
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 222-238
Technical Note / dx.doi.org/10.13182/NSE75-A26754
Albedo-Adjusted Fast-Neutron Diffusion Coefficients in Reactor Reflectors
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 239-245
Technical Note / dx.doi.org/10.13182/NSE75-A26755
Exact Calculations of First Moment in a Simple Neutronic System
Nuclear Science and Engineering / Volume 57 / Number 3 / July 1975 / Pages 245-247
Technical Note / dx.doi.org/10.13182/NSE75-A26756
