Number 1 | Number 2 | Number 3
An Analytical Approach to Continuous Reactor Refueling
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 1-13
Technical Paper / dx.doi.org/10.13182/NSE69-A21110
The Thermal Utilization in Noncylindrical Reactor Cells Containing a Cylindrical Fuel Rod
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 14-26
Technical Paper / dx.doi.org/10.13182/NSE69-A21111
Critical Experiments for the Repetitively Pulsed Reactor SORA
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 27-44
Technical Paper / dx.doi.org/10.13182/NSE69-A21112
Moderator Studies for a Repetitively Pulsed Test Facility (RPTF)
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 45-69
Technical Paper / dx.doi.org/10.13182/NSE69-A21113
Pulsed-Neutron Diffusion Parameters in Spherical Water Systems
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 70-79
Technical Paper / dx.doi.org/10.13182/NSE69-A21114
Slow-Neutron Scattering by Diphenyl
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 80-87
Technical Paper / dx.doi.org/10.13182/NSE69-A21115
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 88-90
Technical Paper / dx.doi.org/10.13182/NSE69-A21116
The Neutron Spectrum from a Fission Source in Graphite
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 91-103
Technical Paper / dx.doi.org/10.13182/NSE69-A21117
An Improved Neutron Decay Spectrometer
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 104-112
Technical Paper / dx.doi.org/10.13182/NSE69-A21118
Gamma-Ray Transmission Through Inhomogeneous Layers
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 113-117
Technical Paper / dx.doi.org/10.13182/NSE69-A21119
Longitudinal Hydraulic Wave Phenomena in Fuel Assemblies Consisting of Concentric Fuel Elements
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 118-126
Technical Paper / dx.doi.org/10.13182/NSE69-A21120
An Experimental Study of Vibration of Flexible Cylinders Induced by Nominally Axial Flow
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 127-138
Technical Paper / dx.doi.org/10.13182/NSE69-A21121
Sn Calculation of Highly Forward Peaked Neutron Angular Fluxes Using Asymmetrical Quadrature Sets
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 139-141
Technical Note / dx.doi.org/10.13182/NSE69-A21122
Perturbation Methods in Nuclear Reactors from the Importance Conservation Principle
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 141-144
Technical Note / dx.doi.org/10.13182/NSE69-A21123
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 144-149
Technical Note / dx.doi.org/10.13182/NSE69-A21124
Neutron Source Inversion Levels and Source-Drop Technique for Negative Reactivity Measurements
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 149-152
Technical Note / dx.doi.org/10.13182/NSE69-A21125
Neutron-Wave Propagation Through a Crystalline Moderator—III: Ice
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 152-154
Technical Note / dx.doi.org/10.13182/NSE69-A21126
Some Similarities Between Boiling and Condensing Flow
Nuclear Science and Engineering / Volume 35 / Number 1 / January 1969 / Pages 154-156
Technical Note / dx.doi.org/10.13182/NSE69-A21127
Surface Depletion in the Vacuum Distillation of Metals from Bismuth
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 159-164
Technical Paper / dx.doi.org/10.13182/NSE69-A21131
Simplified Analysis of Coolant Flow and Outlet Temperature in Gas-Cooled Nuclear Reactor Cores
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 165-175
Technical Paper / dx.doi.org/10.13182/NSE69-A21132
Linear Dynamics Model for Steam Cooled Fast Power Reactors
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 176-189
Technical Paper / dx.doi.org/10.13182/NSE69-A21133
Two-Phase Fluid Modeling—The Critical Heat Flux
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 190-199
Technical Paper / dx.doi.org/10.13182/NSE69-A21134
An Integrated Analytical Model for the Evaluation of Two-Phase Flow Stability
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 200-210
Technical Paper / dx.doi.org/10.13182/NSE69-A21135
Instability Bounds in Linearly Stable Systems
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 211-219
Technical Paper / dx.doi.org/10.13182/NSE69-A21136
Shielding of Neutrons from 80-MeV Alpha-Particle Bombardment of Tantalum
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 220-226
Technical Paper / dx.doi.org/10.13182/NSE69-A21137
Time Spectra from Spheres Pulsed with 14-MeV Neutrons
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 227-239
Technical Paper / dx.doi.org/10.13182/NSE69-A21138
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 240-248
Technical Paper / dx.doi.org/10.13182/NSE69-A21139
Reactor-Noise Analysis: The Covariance Method via Polarity Detection
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 249-258
Technical Paper / dx.doi.org/10.13182/NSE69-A21140
Measurement of the Thermal-Neutron Extrapolation Length in a Pulsed Water System
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 259-266
Technical Paper / dx.doi.org/10.13182/NSE69-A21141
Critical Measurements on an Enriched Uranium Solution System
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 267-276
Technical Paper / dx.doi.org/10.13182/NSE69-A21142
The Effect of Linearly Anisotropic Neutron Scattering on Disadvantage Factor Calculations
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 277-282
Technical Paper / dx.doi.org/10.13182/NSE69-A21143
Modeling Relationships for Radiation Transport Within Ducts and Other Cavities in Shields
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 283-285
Technical Note / dx.doi.org/10.13182/NSE69-A21144
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 285-289
Technical Note / dx.doi.org/10.13182/NSE69-A21145
A Method for Treating the Neutron Leakage in Small Exponential Cores
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 289-295
Technical Note / dx.doi.org/10.13182/NSE69-A21146
Monte Carlo Interpretation of a 238U Spherical Shell Transmission Experiment at 23 keV
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 295-297
Technical Note / dx.doi.org/10.13182/NSE69-A21147
Multilevel Effects on Infinite Dilution Resonance Integrals
Nuclear Science and Engineering / Volume 35 / Number 2 / February 1969 / Pages 297-298
Technical Note / dx.doi.org/10.13182/NSE69-A21148
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 303-318
Technical Paper / dx.doi.org/10.13182/NSE69-A20009
Space-Time Kinetics for Heterogeneous Reactor Models
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 319-331
Technical Paper / dx.doi.org/10.13182/NSE69-A20010
Application of Laguerre Polynomials in the Analysis of Neutron-Wave Propagation
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 332-341
Technical Paper / dx.doi.org/10.13182/NSE69-A20011
Axial Propagation of Neutron Waves in Heterogeneous Media
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 342-349
Technical Paper / dx.doi.org/10.13182/NSE69-A20012
Energy-Dependent Shielding Factors for 235U Foils from Transmission Experiments
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 350-357
Technical Paper / dx.doi.org/10.13182/NSE69-A20013
Material Buckling Measurements with 2.1 wt% 235U Enriched Uranium Tubes in Light Water
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 358-363
Technical Paper / dx.doi.org/10.13182/NSE69-A20014
Average s- and p-Wave Resonance Parameters of 115In and 127I
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 364-370
Technical Paper / dx.doi.org/10.13182/NSE69-A20015
Neutron Dose Rate Attenuation by Iron and Lead
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 371-375
Technical Paper / dx.doi.org/10.13182/NSE69-A20016
Fast-Neutron Spectrum and Dose-Rate Measurements in Water and Aluminum-Water Laminations
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 376-383
Technical Paper / dx.doi.org/10.13182/NSE69-A20017
Effects of Condensation on the Transport of Matter from Vapor and Noncondensable Gas Mixtures
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 384-393
Technical Paper / dx.doi.org/10.13182/NSE69-A20018
The Effect of Coolant pH on Reactor Reactivity
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 394-395
Technical Note / dx.doi.org/10.13182/NSE69-A20019
A Nonlinear Xenon Stability Criterion for a Spatially Dependent Reactor Model
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 395-396
Technical Note / dx.doi.org/10.13182/NSE69-A20020
Review of Epithermal Integral Measurements of Neutron Capture end Fission in 233U
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 396-398
Technical Note / dx.doi.org/10.13182/NSE69-A20021
A Comprehensive System for Computer Gain Changing of Scintillation Spectra
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 399-401
Technical Note / dx.doi.org/10.13182/NSE69-A20022
Differential Dose Albedo for Fast Neutrons
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 401-405
Technical Note / dx.doi.org/10.13182/NSE69-A20023
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 405-406
Technical Note / dx.doi.org/10.13182/NSE69-A20024
The Attenuation of Space Protons by Thin Cylindrical Shell and Slab Disk Shields
Nuclear Science and Engineering / Volume 35 / Number 3 / March 1969 / Pages 406-408
Technical Note / dx.doi.org/10.13182/NSE69-A20025