Number 1 | Number 2 | Number 3
The Solution of a Diffusion-Convective Corrosion Problem
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 1-6
Technical Paper / dx.doi.org/10.13182/NSE68-A20911
An Evaluation of the Departure from Nucleate Boiling in Bundles of Reactor Fuel Rods
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 7-15
Technical Paper / dx.doi.org/10.13182/NSE68-A20912
The Total Neutron Cross Section of 115-Day Tantalum-182 from 0.01 to 1000 eV
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 16-23
Technical Paper / dx.doi.org/10.13182/NSE68-A20913
Absolute Radiative Capture Cross Section for Fast Neutrons in 238U
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 24-30
Technical Paper / dx.doi.org/10.13182/NSE68-2
Neutron Scattering by Reactor-Grade Graphite
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 31-40
Technical Paper / dx.doi.org/10.13182/NSE68-A20915
Slow-Neutron Inelastic Scattering and the Dynamics of Heavy Water
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 41-50
Technical Paper / dx.doi.org/10.13182/NSE68-A20916
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 51-55
Technical Paper / dx.doi.org/10.13182/NSE68-A20917
Measurement of Reactor Fluctuation Spectra and Subcritical Reactivity
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 56-64
Technical Paper / dx.doi.org/10.13182/NSE68-A20918
Thermal-Neutron Decay in Small Systems
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 65-80
Technical Paper / dx.doi.org/10.13182/NSE68-A20919
Time-Dependent Neutron Thermalization in Finite Light Water Systems
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 81-92
Technical Paper / dx.doi.org/10.13182/NSE68-A20920
A Modal Analysis of Neutron-Flux Spatial Oscillation
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 93-105
Technical Paper / dx.doi.org/10.13182/NSE68-A20921
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 106-118
Technical Paper / dx.doi.org/10.13182/NSE68-A20922
A Transport Theory of Neutron Wave Propagation in Polycrystalline Media
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 119-127
Technical Paper / dx.doi.org/10.13182/NSE68-A20923
A Three-Dimensional PN Spherical Harmonics Theory in Cylindrical Geometry
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 128-138
Technical Paper / dx.doi.org/10.13182/NSE68-A20924
Investigation of the Criticality of Low-Enrichment Uranium Cylinders
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Page 139
Technical Note / dx.doi.org/10.13182/NSE68-A20925
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 139-141
Technical Note / dx.doi.org/10.13182/NSE68-A20926
The Approach to the Asymptotic Density of Neutrons Slowing Down from a Delta-Function Source
Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 141-143
Technical Note / dx.doi.org/10.13182/NSE68-A20927
Placzek-Type Oscillations in General Neutron Slowing Down
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 147-150
Technical Paper / dx.doi.org/10.13182/NSE68-A20652
PN Blackness Theory in Plane Geometry
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 151-161
Technical Paper / dx.doi.org/10.13182/NSE68-A20653
Optimal Control of Xenon-Power Spatial Transients
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 162-168
Technical Paper / dx.doi.org/10.13182/NSE68-A20654
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 169-186
Technical Paper / dx.doi.org/10.13182/NSE68-A20655
Slow Neutron Scattering from Water
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 187-194
Technical Paper / dx.doi.org/10.13182/NSE68-A20656
Inelastic Thermal-Neutron Scattering by Liquid D2O
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 195-208
Technical Paper / dx.doi.org/10.13182/NSE68-A20657
Thermal-Neutron Diffusion in Light and Heavy Water
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 209-217
Technical Paper / dx.doi.org/10.13182/NSE68-A20658
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 218-224
Technical Paper / dx.doi.org/10.13182/NSE68-A20659
Determination of Reactor Kinetic Parameters by Photon Observation
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 225-237
Technical Paper / dx.doi.org/10.13182/NSE68-A20660
Spatially Dependent Resonance Neutron Spectra in a Slab of Depleted Uranium
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 238-248
Technical Paper / dx.doi.org/10.13182/NSE68-A20661
Description of Anisotropic Scattering in the Double Pl Method by Means of Anisotropy Functions
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 249-251
Technical Note / dx.doi.org/10.13182/NSE68-A20662
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 251-254
Technical Note / dx.doi.org/10.13182/NSE68-A20663
Numerical Solution of the Boltzmann Integral Equation—A Multigroup Benchmark Calculation
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 255-257
Technical Note / dx.doi.org/10.13182/NSE68-A20664
Application of Variational Synthesis to the Optimal Control of a Point Reactor Model
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 257-260
Technical Note / dx.doi.org/10.13182/NSE68-A20665
Analytic Resonance Integral Formulae
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 260-262
Technical Note / dx.doi.org/10.13182/NSE68-A20666
Time and Space Relaxation Constants of Neutrons in a Proton Gas
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 262-264
Technical Note / dx.doi.org/10.13182/NSE68-A20667
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 264-265
Technical Note / dx.doi.org/10.13182/NSE68-A20668
Total Neutron Cross Section of Water
Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 265-267
Technical Note / dx.doi.org/10.13182/NSE68-A20669
Performance of Gas-Cooled Fast Reactors with Artificially Roughened Fuel Elements
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 271-283
Technical Paper / dx.doi.org/10.13182/NSE68-A19234
Monte Carlo Integration of the Adjoint Gamma-Ray Transport Equation
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 284-290
Technical Paper / dx.doi.org/10.13182/NSE68-A19235
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 291-296
Technical Paper / dx.doi.org/10.13182/NSE68-A19236
Multigroup Treatment of Neutron Transport in Plane Geometry
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 297-302
Technical Paper / dx.doi.org/10.13182/NSE68-A19237
On the Quantum-Mechanical Foundations of the Neutron Transport Theory
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 303-306
Technical Paper / dx.doi.org/10.13182/NSE68-A19238
Solution of the Two-Group Neutron Transport Equation—I
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 307-317
Technical Paper / dx.doi.org/10.13182/NSE68-A19239
Solution of the Two-Group Neutron Transport Equation—II
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 318-326
Technical Paper / dx.doi.org/10.13182/NSE68-A19240
Numerical Solutions of Boundary Value Problems
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 327-335
Technical Paper / dx.doi.org/10.13182/NSE68-A19241
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 336-339
Technical Paper / dx.doi.org/10.13182/NSE68-A19242
Some Consideration of Dose Buildup Factor for a 60Co Cylindrical Source with Shell-Shaped Shield
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 340-341
Technical Note / dx.doi.org/10.13182/NSE68-A19243
First-Flight Escape Probability for Bodies Containing a Central Black Region
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 341-343
Technical Note / dx.doi.org/10.13182/NSE33-03-341
Space-Dependent Effects in Rossi-Alpha Experiments
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 344-348
Technical Note / dx.doi.org/10.13182/NSE68-A19245
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 348-350
Technical Note / dx.doi.org/10.13182/NSE68-A19246
Infinite Dilution Resonance Absorption Integrals of Hafnium
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 350-352
Technical Note / dx.doi.org/10.13182/NSE68-A19247
Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 352-354
Technical Note / dx.doi.org/10.13182/NSE68-A19248