Number 1
- Table of Contents
- A One-Group Model for Thermal Activation Calculations
- Let the Reactor Prevent Xenon Instability
- Thermal Neutron Flux in a Cell with Temperature Discontinuities
- Local Flux Distributions in ORR Fuel Elements
- Natural Abundances of Er172 and Yb167
- Precision Measurements of the Slow Neutron Absorption Cross Sections of Normal Boron Standards
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE61-A25858
The Determination of Lattice Parameters by Means of Measurements on a Single Fuel Element
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 16-25
Technical Paper | doi.org/10.13182/NSE61-A25859
Expansion Losses in Two-Phase Flow
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 26-31
Technical Paper | doi.org/10.13182/NSE61-A25860
Extraction of Plutonium from Uranium by Liquid Magnesium
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 32-34
Technical Paper | doi.org/10.13182/NSE61-A25861
Validity of the Homogenization Approximation for End-Leakage Calculations
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 35-40
Technical Paper | doi.org/10.13182/NSE61-A25862
Intensity of Unscattered Gamma Rays inside Cylindrical Self-Absorbing Sources
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 41-46
Technical Paper | doi.org/10.13182/NSE61-A25863
SM-2 Flexible Critical Experiments
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 47-54
Technical Paper | doi.org/10.13182/NSE61-A25864
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 55-58
Technical Paper | doi.org/10.13182/NSE61-A25865
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 59-63
Technical Paper | doi.org/10.13182/NSE61-A25866
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 64-70
Technical Paper | doi.org/10.13182/NSE61-A25867
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 71-77
Technical Paper | doi.org/10.13182/NSE61-A25868
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 78-81
Technical Paper | doi.org/10.13182/NSE61-A25869
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 82-86
Technical Paper | doi.org/10.13182/NSE61-A25870
Nuclear Science and Engineering | Volume 9 | Number 1 | January 1961 | Pages 87-90
Technical Paper | doi.org/10.13182/NSE61-A25871
Number 2
- Table of Contents
- The Density of Dilute Solutions of Copper in Liquid Lead
- Reactivity Effect of (n, 2n) Reactions in D2O
- Formulas for Thermal Reactors with Some Resonance Fission
- Prediction of Thermal-Neutron Fluxes in the Bulk Shielding Facility from Lid Tank Shielding Facility Data
- Failure of Neutron Transport Approximations in Small Cells in Cylindrical Geometry
- Handbook of Chemistry and Physics
- Management of Nuclear Materials
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 105-119
Cold Neutron Beams from Small Low-Temperature Moderators in Reactors
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 120-126
Error Propagation in Hot-Spot, Hot-Channel Analysis
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 127-131
Thermal Neutron Absorption Cross Sections by the Pulsed Source Method
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 132-136
Radiation Damage in Steel: Considerations Involving the Effect of Neutron Spectra
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 137-147
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 148-150
Comparison Theorems for the Estimation of Criticality in Bare, One-Velocity Reactors
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 151-156
Neutron Thermalization and Diffusion in Pulsed Media
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 157-167
Measurements of Neutron Spectra in Water, Polyethylene, and Zirconium Hydride
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 168-184
On the Solution of Transport Problems by Conditional Monte Carlo
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 185-197
Flux Perturbations by Thermal Neutron Detectors
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 198-210
Preparation and Characteristics of ThO2-Bi Slurries
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 211-220
Age of Fission Energy Neutrons to Indium Resonance in Water
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 221-240
An Approach to Reactor Physics Using Results of Integral Experiments
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 241-259
On the Maximization of the Sensitivity of a Fuel Assay Reactor
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 260-270
The Influence of Pressure on Boiling Water Reactor Dynamic Behavior at Atmospheric Pressure
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 271-280
Number 3
- Table of Contents
- Regarding “Elastic-Plastic Thermal Stresses in Tubes Subjected to Uniform Heat Generation Evaluation of Experimental Results Obtained Using Graphite Tubes”
- Rebuttal
- Slowing-Down Time of Neutrons in Water
- Effect of Interference between Resonance and Potential Scattering on Resonance Absorption
- FNR Shim-Safety Rod Deformations
- Beta-Gamma Delayed Coincidence Method for Resonance Escape Measurements
- Re: "An H2O-D2O Moderated Reactor"
- Crack Formation in Uranium
- Book Review
- Book Review
Reactivity Worth of the Central Fuel Element in the Bulk Shielding Reactor-I
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 291-298
Technical Paper | doi.org/10.13182/NSE61-A25879
Niobium-20 w/o Uranium, High-Temperature Metallic Fuel of the Future
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 299-304
Technical Paper | doi.org/10.13182/NSE61-A25880
Time-Dependent Thermal-Neutron Energy Spectra in a Monatomic Heavy Gas
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 305-313
Technical Paper | doi.org/10.13182/NSE61-A25881
On the Design and Management of Fast Reactor Blankets
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 314-322
Technical Paper | doi.org/10.13182/NSE61-A25882
Formal Heat Transfer Solutions
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 323-331
Technical Paper | doi.org/10.13182/NSE61-A25883
Effect of Specific Power on Fuel Reactivity and Costs in Thorium-Fueled Reactors
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 332-340
Technical Paper | doi.org/10.13182/NSE61-A25884
The Resonance Fission Integrals of U235, Pu239, and Pu241
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 341-345
Technical Paper | doi.org/10.13182/NSE61-A25885
Circulating Fused-Salt Fuel Irradiation Test Loop
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 346-356
Technical Paper | doi.org/10.13182/NSE61-A25886
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 357-361
Technical Paper | doi.org/10.13182/NSE61-A25887
The Solution of the Reactor Kinetics Equations for Large and Small Excursions
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 362-366
Technical Paper | doi.org/10.13182/NSE61-A25888
The Effect of Diffusion upon the Initial Phases of the Thermalization of Neutrons
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 367-369
Technical Paper | doi.org/10.13182/NSE61-A25889
New Analytical Formula for Dancoff Correction for Cylindrical Fuel Lattices
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 370-376
Technical Paper | doi.org/10.13182/NSE61-A25890
Minimum Critical Dimensions for Water Solutions
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 377-390
Technical Paper | doi.org/10.13182/NSE61-A25891
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 391-398
Technical Paper | doi.org/10.13182/NSE61-A25892
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 399-407
Technical Paper | doi.org/10.13182/NSE61-A25893
Number 4
Diffusion of Lanthanides and Actinides from Graphite at High Temperatures
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 417-420
Technical Paper | doi.org/10.13182/NSE61-A25905
Experimental Studies of U238 Resonance Neutron Capture in UO2 Fuel Rods
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 421-429
Technical Paper | doi.org/10.13182/NSE61-A25906
The Effects of Atomic Motions on the Moderation of Neutrons
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 430-441
Technical Paper | doi.org/10.13182/NSE61-A25907
Transient Flow Performance in a Multiloop Nuclear Reactor System
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 442-454
Technical Paper | doi.org/10.13182/NSE61-A25908
Purification of Irradiated Tributyl Phosphate by Distillation in Kerosene-Type Diluent
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 455-461
Technical Paper | doi.org/10.13182/NSE61-A25909
High-Frequency Surface Thermal Fatigue Cycling of Inconel at 1405°F
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 462-474
Technical Paper | doi.org/10.13182/NSE61-A25910
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 475-487
Technical Paper | doi.org/10.13182/NSE61-A25911
New Developments in Uranium-Zirconium Alloy Fuel Reprocessing
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 488-494
Technical Paper | doi.org/10.13182/NSE61-A25912
Equal Charge Displacement Rule in Fission Product Poisoning
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 495-499
Technical Paper | doi.org/10.13182/NSE61-A25913
Solid State Electrolysis in Yttrium Metal
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 500-506
Technical Paper | doi.org/10.13182/NSE61-A25914
The Resonance Integral of Thorium Metal Rods
Nuclear Science and Engineering | Volume 9 | Number 4 | April 1961 | Pages 507-518
Technical Paper | doi.org/10.13182/NSE61-A25915