Volume 32
Number 3
Reactor Physics Parameters of 1.03% Enriched Uranium Metal, D2O Moderated Lattices
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 283-291
Technical Paper / dx.doi.org/10.13182/NSE68-A20210
Prompt Neutron Decay and Reactivity Measurements in Subcritical Uranium Metal Cylinders
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 292-301
Technical Paper / dx.doi.org/10.13182/NSE68-A20211
Anisotropic Neutron Slowing Down in Aluminum-Water Mixtures-I: Experiments
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 302-312
Technical Paper / dx.doi.org/10.13182/NSE68-A20212
Anisotropic Neutron Slowing Down in Aluminum-Water Mixtures-II: Monte Carlo Calculations
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 313-318
Technical Paper / dx.doi.org/10.13182/NSE68-A20213
Monte Carlo Criticality Calculations for Thermal Reactors
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 319-331
Technical Paper / dx.doi.org/10.13182/NSE68-A20214
The Asymmetric Source Method of Measuring Reactor Shutdown
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 332-341
Technical Paper / dx.doi.org/10.13182/NSE68-A20215
Asymptotic Solutions to the Transport Equation for a Plane Lattice
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 342-349
Technical Paper / dx.doi.org/10.13182/NSE68-A20216
The Thermal-Neutron Milne Problem and the Albedo of a Semi-Infinite Absorbing Medium-I: Theory
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 350-356
Technical Paper / dx.doi.org/10.13182/NSE68-A20217
Ray Effects in Discrete Ordinates Equations
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 357-369
Technical Paper / dx.doi.org/10.13182/NSE68-4
Reflection and Refraction of Neutron Diffusion Waves
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 370-376
Technical Paper / dx.doi.org/10.13182/NSE68-A20219
Parametric Fit of the Total Neutron Cross Section of Manganese from 0.01 eV to 50 keV
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 377-384
Technical Paper / dx.doi.org/10.13182/NSE68-A20220
Calculation of the Penetration of Gamma Rays Through Two-Layer Slabs
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 385-391
Technical Paper / dx.doi.org/10.13182/NSE68-A20221
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 392-406
Technical Paper / dx.doi.org/10.13182/NSE68-A20222
Diffusion Model for Release of Fission Products from Coated Particle Fuels
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 407-416
Technical Paper / dx.doi.org/10.13182/NSE68-A20223
Interrelation of Nuclear Reactor Kinetic Experiments
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 417-420
Technical Note / dx.doi.org/10.13182/NSE68-A20224
Nuclear Resonance Spacings and Synthetic Kernels
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 420-422
Technical Note / dx.doi.org/10.13182/NSE68-A20225
Exact Treatment of the Resonance Absorption of Neutrons of Intermediate Energy
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 422-425
Technical Note / dx.doi.org/10.13182/NSE68-A20226
On the Application of Time-Synthesis Techniques to Coupled Core Reactors
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 425-429
Technical Note / dx.doi.org/10.13182/NSE68-A20227
Statistical Analysis of Static Power Tilting in Reactors Due to Manufacturing Tolerances
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 429-430
Technical Note / dx.doi.org/10.13182/NSE68-A20228
The Effect of Fission Density on Fission-Gas Release
Nuclear Science and Engineering / Volume 32 / Number 3 / June 1968 / Pages 430-431
Technical Note / dx.doi.org/10.13182/NSE68-A20229
