Number 1 | Number 2 | Number 3 | Number 4
A Differential Calorimeter for Radiation-Induced Power
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 1-5
Technical Paper / dx.doi.org/10.13182/NSE64-A18136
A Comparison of Methods of Determining Burnup on Uranium Dioxide Fuel Test Specimens
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 6-17
Technical Paper / dx.doi.org/10.13182/NSE64-A18137
Titanium and Titanium Alloys in Mercury - Some Observations on Corrosion and Inhibition
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 18-30
Technical Paper / dx.doi.org/10.13182/NSE64-A18138
Theoretical and Experimental Study of Fatigue in Photomultiplier Tubes
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 31-48
Technical Paper / dx.doi.org/10.13182/NSE64-A18139
The Calculation of the Thermal Utilization and Disadvantage Factor in Uranium/Water Lattices
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 49-68
Technical Paper / dx.doi.org/10.13182/NSE64-A18140
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 69-79
Technical Paper / dx.doi.org/10.13182/NSE64-A18141
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 80-89
Technical Paper / dx.doi.org/10.13182/NSE64-A18142
The Application of “One-Group” Transport Theory to β-Ray Dosimetry
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 90-96
Technical Paper / dx.doi.org/10.13182/NSE64-A18143
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 97-104
Technical Paper / dx.doi.org/10.13182/NSE64-A18144
Reactions O17 (n, p)N17 and O18 (n, d)N17 with Reactor Neutrons
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 105-109
Technical Paper / dx.doi.org/10.13182/NSE64-A18145
Production of Transuranium Elements in a Thermonuclear Explosion - Anacostia
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 110-112
Technical Paper / dx.doi.org/10.13182/NSE64-A18146
Economy of Experiment in Dose Albedo
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 113-115
Technical Paper / dx.doi.org/10.13182/NSE64-A18147
Lattice-Parameter Measurements for Solid and Concentric Tubes of Uranium Fuel in Graphite Lattices
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 116-125
Technical Paper / dx.doi.org/10.13182/NSE64-A18148
Elastic Scattering of Fast Neutrons from U235
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 126-129
Technical Paper / dx.doi.org/10.13182/NSE64-A18149
Theoretical Analysis of the Exponential Experiment in Natural Uranium
Nuclear Science and Engineering / Volume 18 / Number 1 / January 1964 / Pages 130-136
Technical Paper / dx.doi.org/10.13182/NSE64-A18150
Release of Fission Products During In-Pile Melting of UO2
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 151-162
Technical Paper / dx.doi.org/10.13182/NSE64-1
Application of Synthesis Techniques to Problems Involving Time Dependence
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 163-176
Technical Paper / dx.doi.org/10.13182/NSE64-A18315
The Recovery of Protactinium and Uranium from Molten Fluoride Systems by Precipitation as Oxides
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 177-181
Technical Paper / dx.doi.org/10.13182/NSE64-A18316
Inelastic Neutron Scattering in Liquid Methane and Liquid Parahydroge
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 182-188
Technical Paper / dx.doi.org/10.13182/NSE64-A18317
The Leachability of Fission Products from Uranium-Impregnated Graphite Heated at High Temperature
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 189-199
Technical Paper / dx.doi.org/10.13182/NSE64-A18318
Design of a Pressure Balanced Control Rod
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 200-206
Technical Paper / dx.doi.org/10.13182/NSE64-A18319
Methods for Determining the Energy Release in Hypothetical Fast-Reactor Meltdown Accidents
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 207-219
Technical Paper / dx.doi.org/10.13182/NSE64-A18320
Evaluation of Two-Region-Reactor Parameters by Random Noise Measurements
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 220-229
Technical Paper / dx.doi.org/10.13182/NSE64-A18321
Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 230-235
Technical Paper / dx.doi.org/10.13182/NSE64-A18322
Determination of Cadmium Burnup in Reactor Control Rods by Neutron Radiography
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 236-241
Technical Paper / dx.doi.org/10.13182/NSE64-A18323
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 242-245
Technical Paper / dx.doi.org/10.13182/NSE64-A18324
The Effective Resonance Integral of Thorium Oxide Rods
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 246-259
Technical Paper / dx.doi.org/10.13182/NSE64-A18325
The Energy-Dependent Milne Problem with a Simple Scattering Kernel
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 260-270
Technical Paper / dx.doi.org/10.13182/NSE64-A18326
A Nonlinear Analysis of a Reactor with Two Temperature Coefficients
Nuclear Science and Engineering / Volume 18 / Number 2 / February 1964 / Pages 271-279
Technical Paper / dx.doi.org/10.13182/NSE64-A18327
Fission-Gas Release from Pyrolytic-Carbon-Coated Fuel Particles During Irradiation
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 301-318
Technical Paper / dx.doi.org/10.13182/NSE64-A20051
In-Pile Experiments on Meltdown of EBR-II Mark I Fuel Elements in Stagnant Sodium
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 319-328
Technical Paper / dx.doi.org/10.13182/NSE64-A20052
Boundary Conditions for Parallel Channel Flow
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 329-334
Technical Paper / dx.doi.org/10.13182/NSE64-A20053
A Digital Computer Solution for Space-Dependent Neutron Kinetics Equations
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 335-350
Technical Paper / dx.doi.org/10.13182/NSE64-A20054
Temperature Dependence of Neutron-Pulse Parameters in H2O
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 351-362
Technical Paper / dx.doi.org/10.13182/NSE64-A20055
An Eigenvalue Method for the Calculation of Nuclear Burnup
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 363-369
Technical Paper / dx.doi.org/10.13182/NSE64-A20056
An Improved Spherical-Harmonics Method
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 370-375
Technical Paper / dx.doi.org/10.13182/NSE64-A20057
Neutron-Spectrum Measurements in H2O, CH2 and C6H6
Nuclear Science and Engineering / Volume 18 / Number 3 / March 1964 / Pages 376-399
Technical Paper / dx.doi.org/10.13182/NSE64-A20058
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 421-425
Technical Paper / dx.doi.org/10.13182/NSE64-A18759
Fission-Product Behavior in Direct-Contact-Core Liquid-Metal-Fueled Reactors
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 426-434
Technical Paper / dx.doi.org/10.13182/NSE64-A18760
Delayed Neutron Economy and Control in a Direct-Contact-Core Liquid-Metal-Fueled Reactor
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 435-442
Technical Papers / dx.doi.org/10.13182/NSE64-A18761
The Effect of Axial Heat Conduction in Fuel Plates on Maximum Heat Flow Rates and Temperatures
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 443-447
Technical Paper / dx.doi.org/10.13182/NSE64-A18762
Intercomparison of Fast-Neutron Flux Monitors in a Hollow Fuel Element in Pluto
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 448-458
Technical Paper / dx.doi.org/10.13182/NSE64-A18763
Numerical Integration of the Spherical-Harmonics Equations
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 459-467
Technical Paper / dx.doi.org/10.13182/NSE64-A18764
Determination of Fast-Neutron Dose by Nickel Activation
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 468-473
Technical Paper / dx.doi.org/10.13182/NSE64-A18765
Measurements of Leakage-Neutron Energy Spectra
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 474-480
Technical Paper / dx.doi.org/10.13182/NSE64-A18766
Reactor Kinetics Analysis by an Inverse Method
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 481-490
Technical Paper / dx.doi.org/10.13182/NSE64-A18767
Neutron Transport in Cylindrical Rods
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 491-507
Technical Paper / dx.doi.org/10.13182/NSE64-A18768
Closed-Loop Dynamics of Nuclear Rocket Engines with Topping Turbine Drive
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 508-513
Technical Paper / dx.doi.org/10.13182/NSE64-A18769
Fuel-Importance Function and Minimum Critical Mass
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 514-517
Technical Paper / dx.doi.org/10.13182/NSE64-A18770
Nuclear Science and Engineering / Volume 18 / Number 4 / April 1964 / Pages 518-524
Technical Paper / dx.doi.org/10.13182/NSE64-A18771