Number 1
Resonance Escape Probability in Hydrogenous Lattices
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 1-4
Technical Paper | doi.org/10.13182/NSE59-A27320
Perturbation Theory of Control Elements. II
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 5-10
Technical Paper | doi.org/10.13182/NSE59-A27321
The Utilization of a Cold Trap to Stabilize Suspensions of UO2 in NaK
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 11-14
Technical Paper | doi.org/10.13182/NSE59-A27322
Effect of Radiation on Corrosion of Structural Materials by Molten Fluorides
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 15-20
Technical Paper | doi.org/10.13182/NSE59-A27323
Theory of Pulsed Neutron Experiments in Multiplying Media
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 21-27
Technical Paper | doi.org/10.13182/NSE59-A27324
Nuclear Radiation Heating: Preliminary Design Considerations
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 28-31
Technical Paper | doi.org/10.13182/NSE59-A27325
The Width of the 1 ev Resonance in Plutonium-240
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 32-35
Technical Paper | doi.org/10.13182/NSE59-A27326
Iterative Solutions to the P1 and Double-P1 Equations1
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 36-44
Technical Paper | doi.org/10.13182/NSE59-A27327
Intermediate Energy Neutron Leakage Through Iron
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 45-48
Technical Paper | doi.org/10.13182/NSE59-A27328
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 49-54
Technical Paper | doi.org/10.13182/NSE59-A27329
Half Lives of N16, Mg27, Al28, S37, and Rh104m2
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 55-56
Technical Paper | doi.org/10.13182/NSE59-A27330
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 57-60
Technical Paper | doi.org/10.13182/NSE59-A27331
Fast Fission Effect in Lattices of Natural Uranium and Heavy Water
Nuclear Science and Engineering | Volume 5 | Number 1 | January 1959 | Pages 61-67
Technical Paper | doi.org/10.13182/NSE59-A27332
Number 2
A Simple Analytical Formulation of the Dancoff Correction
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 75-77
Technical Paper | doi.org/10.13182/NSE59-A25559
A Kinetic Study of Irradiation Induced Phase Changes in Uranium-9 w/o Molybdenum Alloy1
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 78-87
Technical Paper | doi.org/10.13182/NSE59-A25560
Sources of Error in Reactivity Determinations by Means of Asymptotic Period Measurements1
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 88-98
Technical Paper | doi.org/10.13182/NSE59-A25561
Inelastic Scattering of Cold Neutrons from Several Hydrogenous Liquids1
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 99-104
Technical Paper | doi.org/10.13182/NSE59-A25562
Plutonium Recycle in the Calder Hall Type Reactor
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 105-119
Technical Paper | doi.org/10.13182/NSE59-A25563
Operating Characteristics of a Graphite-Moderated Subcritical Assembly
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 120-126
Technical Paper | doi.org/10.13182/NSE59-A25564
The Computation of Excess Reactivity From Power Traces
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 127-131
Technical Paper | doi.org/10.13182/NSE59-A25565
Period-Reactivity Relations Determined Directly From Prompt-Burst Neutron Decay Data
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 132-136
Technical Paper | doi.org/10.13182/NSE59-A25566
Number 3
- Table of Contents
- Elastic Constants of Polycrystalline Uranium
- Attenuation of 14-Mev Neutrons in Water and in 6-In. Lead and Water
- The Inertia Transient in Reactor Draining
- Plastic Bending of Rods or Tubes with Radial Temperature Distributions
- Note on the Thermal Neutron Spectrum in a Diffusing Medium
- ANS News
Zeta Potentials of ThO2 and of Stainless Steel as Related to Aggregation and Caking
Nuclear Science and Engineering | Volume 5 | Number 3 | March 1959 | Pages 143-149
Technical Paper | doi.org/10.13182/NSE59-A25572
Evaluation of a Bank of Slab-type Control Rods
Nuclear Science and Engineering | Volume 5 | Number 3 | March 1959 | Pages 150-155
Technical Paper | doi.org/10.13182/NSE59-A25573
Calculated Activities and Abundances of U235 Fission Products
Nuclear Science and Engineering | Volume 5 | Number 3 | March 1959 | Pages 156-185
Technical Paper | doi.org/10.13182/NSE59-A25574
Time Constant of Cylindrical Fuel Pin with Axial Coolant Flow
Nuclear Science and Engineering | Volume 5 | Number 3 | March 1959 | Pages 186-189
Technical Paper | doi.org/10.13182/NSE59-A25575
Restricted Minimum Critical Mass
Nuclear Science and Engineering | Volume 5 | Number 3 | March 1959 | Pages 190-194
Technical Paper | doi.org/10.13182/NSE59-A25576
A Note on the Elastic Constants of Uranium
Nuclear Science and Engineering | Volume 5 | Number 3 | March 1959 | Pages 195-196
Technical Paper | doi.org/10.13182/NSE59-A25577
Number 4
The Behavior of a Reactor at Prompt Critical when the Reactivity is a Linear Function of Time
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 207-214
Technical Paper | doi.org/10.13182/NSE59-A25585
Thermal Buckling of Cruciform Control Rods
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 215-218
Technical Paper | doi.org/10.13182/NSE59-A25586
Magnesium-Clad Wedge S-Shaped Fuel Plates for Gas-Cooled Reactors
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 219-224
Technical Paper | doi.org/10.13182/NSE59-A25587
Pile Oscillator Measurements of Eta
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 225-226
Technical Paper | doi.org/10.13182/NSE59-A25588
A UO2—Liquid Metal Slurry Reactor for Economic Power
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 227-236
Technical Paper | doi.org/10.13182/NSE59-A25589
Resonance Escape Probability in Water Lattice
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 237-241
Technical Paper | doi.org/10.13182/NSE59-A25590
A Method of Correlating Burnout Heat Flux Data
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 242-247
Technical Paper | doi.org/10.13182/NSE59-A25591
On the Validity of the Second Fundamental Theorem for Small Reactors
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 248-253
Technical Paper | doi.org/10.13182/NSE59-A25592
The Dynamic Reactivity Interpretation of Pulsed Neutron Measurements
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 254-256
Technical Paper | doi.org/10.13182/NSE59-A25593
A Study of Split Cores for Research Reactors
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 257-263
Technical Paper | doi.org/10.13182/NSE59-A25594
Pile Neutron Capture Cross Sections of Np239
Nuclear Science and Engineering | Volume 5 | Number 4 | April 1959 | Pages 264-268
Technical Paper | doi.org/10.13182/NSE59-A25595
Number 5
On the Termination of Reactor Excursions
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 273-284
Technical Paper | doi.org/10.13182/NSE59-A25599
A Simple Device for Personnel Monitoring of an Accidental Nuclear Reaction
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 285-290
Technical Paper | doi.org/10.13182/NSE59-A25600
Reduced Delayed Neutron Group Representations
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 291-298
Technical Paper | doi.org/10.13182/NSE59-A25601
Thermal Activation Shapes in a Water-Moderated Critical Assembly
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 299-305
Technical Paper | doi.org/10.13182/NSE59-A25602
The Transmission of Neutrons in Multilayered Slab Geometry
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 306-319
Technical Paper | doi.org/10.13182/NSE59-A25603
Measurement of the Doppler Temperature Effect in an EBR-I Type Assembly
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 320-330
Technical Paper | doi.org/10.13182/NSE59-A25604
Determination of Reactor Kinetic Parameters by Pile Noise Analysis
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 331-335
Technical Paper | doi.org/10.13182/NSE59-A25605
The Number of Elastic Collisions in a Finite Lethargy Interval
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 336-337
Technical Paper | doi.org/10.13182/NSE59-A25606
The Thermal Neutron Spectrum in a Heterogeneous Reactor
Nuclear Science and Engineering | Volume 5 | Number 5 | May 1959 | Pages 338-346
Technical Paper | doi.org/10.13182/NSE59-A25607
Number 6
Nucleate Boiling Characteristics of Organic Reactor Coolants
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 349-359
Technical Paper | doi.org/10.13182/NSE59-A25610
Two Region Studies in Slightly Enriched Water-Moderated Uranium and Uranium Dioxide Lattices
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 360-370
Technical Paper | doi.org/10.13182/NSE59-A25611
A Monte Carlo Method for Criticality Problems
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 371-375
Technical Paper | doi.org/10.13182/NSE59-1
Analysis of Reactor Oscillations for Coefficients of Reactivity
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 376-381
Technical Paper | doi.org/10.13182/NSE59-A25613
The Use of Thermally Black Control Sheets
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 382-389
Technical Paper | doi.org/10.13182/NSE59-A25614
Turbulent Liquid-Metal Heat Transfer in Channels
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 390-404
Technical Paper | doi.org/10.13182/NSE59-A25615
Transfer Functions of Distributed Parameter Nuclear Reactor Systems
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 405-414
Technical Paper | doi.org/10.13182/NSE59-A25616