Number 1 | Number 2 | Number 3 | Number 4 | Number 5 | Number 6
Effective Capture Cross Section of Pa-233 for Thermal Reactor Neutrons
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 1-3
Technical Paper / dx.doi.org/10.13182/NSE56-A17653
Estimation of Doppler Effect in Fast Reactors
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 4-19
Technical Paper / dx.doi.org/10.13182/NSE56-A17654
A Direct Comparison of Some Nuclear Properties of U-233 and U-235
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 20-32
Technical Paper / dx.doi.org/10.13182/NSE56-A17655
Tracer Studies on Radiation Damaged Graphite
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 33-52
Technical Paper / dx.doi.org/10.13182/NSE56-A17656
Topsy, A Remotely Controlled Critical Assembly Machine
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 53-61
Technical Paper / dx.doi.org/10.13182/NSE56-A17657
Pile Neutron Cross Sections of the Heavier Plutonium Isotopes
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 62-67
Technical Paper / dx.doi.org/10.13182/NSE56-A17658
The Effective Resonance Integrals of U-238 and Th-232
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 68-79
Technical Paper / dx.doi.org/10.13182/NSE56-A17659
Random Fluctuations in Period-Meter Indications
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 80-91
Technical Paper / dx.doi.org/10.13182/NSE56-A17660
The Powder Metallurgy of Uranium
Nuclear Science and Engineering / Volume 1 / Number 1 / March 1956 / Pages 92-101
Technical Paper / dx.doi.org/10.13182/NSE56-A17661
Calculation of Neutron Radiative Capture Cross Sections
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 103-107
Technical Paper / dx.doi.org/10.13182/NSE56-A17514
An Effective Capture Cross Section of Np239 for Thermal Reactor Neutrons
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 108-111
Technical Paper / dx.doi.org/10.13182/NSE56-A17515
An Unreflected U-235 Critical Assembly
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 112-125
Technical Paper / dx.doi.org/10.13182/NSE56-1
ZPR-III, Argonne's Fast Critical Facility
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 126-134
Technical Paper / dx.doi.org/10.13182/NSE56-A17517
Small Liquid Metal Fueled Reactor Systems
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 135-155
Technical Paper / dx.doi.org/10.13182/NSE56-A17518
The Attenuation of Neutrons by Air Ducts in Shields
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 156-166
Technical Paper / dx.doi.org/10.13182/NSE56-A17519
A Preliminary Study of Superheating Boiling Reactors
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 167-173
Technical Paper / dx.doi.org/10.13182/NSE56-A17520
Delayed Neutron Yields in Pu, U-233, U-238, and Th Relative to Yield in U-235
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 174-184
Technical Paper / dx.doi.org/10.13182/NSE56-A17521
Cyclotron Target for the Irradiation of Chemical Compounds
Nuclear Science and Engineering / Volume 1 / Number 2 / May 1956 / Pages 185-190
Technical Paper / dx.doi.org/10.13182/NSE56-A17522
Fission and Activation Ratios in the EBR
Nuclear Science and Engineering / Volume 1 / Number 3 / July 1956 / Pages 193-203
Technical Paper / dx.doi.org/10.13182/NSE56-A17851
Long Term Variation in Composition and Neutron Yield in Pile Plutonium
Nuclear Science and Engineering / Volume 1 / Number 3 / July 1956 / Pages 204-215
Technical Paper / dx.doi.org/10.13182/NSE56-A17852
The Yields of the Chemical Elements in Thermal Neutron Fission of U-235
Nuclear Science and Engineering / Volume 1 / Number 3 / July 1956 / Pages 216-221
Technical Paper / dx.doi.org/10.13182/NSE56-A17853
The Streaming of Neutrons in Shields
Nuclear Science and Engineering / Volume 1 / Number 3 / July 1956 / Pages 222-238
Technical Paper / dx.doi.org/10.13182/NSE56-A17854
Average and Local Heat Transfer for Cross Flow Through a Tube Bank
Nuclear Science and Engineering / Volume 1 / Number 3 / July 1956 / Pages 239-251
Technical Paper / dx.doi.org/10.13182/NSE56-A17855
Limitations of Multigroup Calculations
Nuclear Science and Engineering / Volume 1 / Number 4 / August 1956 / Pages 253-267
Technical Paper / dx.doi.org/10.13182/NSE56-A18601
The Thermal Neutron Flux in a Square Lattice Cell
Nuclear Science and Engineering / Volume 1 / Number 4 / August 1956 / Pages 268-279
Technical Paper / dx.doi.org/10.13182/NSE56-A18602
Neutron Thermalization I. Heavy Gaseous Moderator
Nuclear Science and Engineering / Volume 1 / Number 4 / August 1956 / Pages 280-312
Technical Paper / dx.doi.org/10.13182/NSE56-A18603
General Problems of the Controlled Thermonuclear Process
Nuclear Science and Engineering / Volume 1 / Number 4 / August 1956 / Pages 313-324
Technical Paper / dx.doi.org/10.13182/NSE56-A18604
Nuclear Science and Engineering / Volume 1 / Number 4 / August 1956 / Pages 325-326
Technical Paper / dx.doi.org/10.13182/NSE56-A18605
Homogeneous Heavy Water Moderated Critical Assemblies. Part 1. Experimental
Nuclear Science and Engineering / Volume 1 / Number 4 / August 1956 / Pages 327-341
Technical Paper / dx.doi.org/10.13182/NSE56-A18606
U-233 Breeder- U-235 Converter Reactor
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 343-354
Technical Paper / dx.doi.org/10.13182/NSE56-A28772
Evaluation of ln E1/E2 for Resonance Neutrons in Uranium Lattices
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 355-358
Technical Paper / dx.doi.org/10.13182/NSE56-A28773
Engineering Hot Channel Factors for Nuclear Reactor Design
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 359-369
Technical Paper / dx.doi.org/10.13182/NSE56-A28774
The Calculation of Maxwellian-Averaged Cross Sections for Resonance Absorbers
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 370-373
Technical Paper / dx.doi.org/10.13182/NSE56-A28775
The Diffusion of Fission Krypton from Metallic Uranium
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 374-390
Technical Paper / dx.doi.org/10.13182/NSE56-A28776
Measurement of Neutron Spectra of the Experimental Breeder Reactor
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 391-408
Technical Paper / dx.doi.org/10.13182/NSE56-A28777
Processing of Power Reactor Fuels
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 409-419
Technical Paper / dx.doi.org/10.13182/NSE56-A28778
Operational Experience with the Borax Power Plant
Nuclear Science and Engineering / Volume 1 / Number 5 / October 1956 / Pages 420-437
Technical Paper / dx.doi.org/10.13182/NSE56-A28779
The Parasite Reactor, a Pressure-Bomb Assembly for Phase Studies under Irradiation
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 443-451
Technical Paper / dx.doi.org/10.13182/NSE56-A18459
Radiolytic Yields of Nitrogen and Hydrogen in Water Boilers
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 452-454
Technical Paper / dx.doi.org/10.13182/NSE56-A18460
Fast Effect in Lattice Reactors
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 455-460
Technical Paper / dx.doi.org/10.13182/NSE56-A18461
A Method of Analysis of Natural Circulation Boiling Systems
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 461-476
Technical Paper / dx.doi.org/10.13182/NSE56-A18462
Maximum Permissible Internal Dose of Radionuclides: Recent Changes in Values
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 477-500
Technical Paper / dx.doi.org/10.13182/NSE56-A18463
Effect of Geometry on Resonance Neutron Absorption in Uranium
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 501-510
Technical Paper / dx.doi.org/10.13182/NSE56-A18464
Sedimentation of Thorium Oxide Slurries at Elevated Temperatures
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 511-521
Technical Paper / dx.doi.org/10.13182/NSE56-A18465
Multiple Neutron Interactions in Resonant Foils
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 522-540
Technical Paper / dx.doi.org/10.13182/NSE56-A18466
Reactivity Gains in NRX Irradiated Slugs
Nuclear Science and Engineering / Volume 1 / Number 6 / December 1956 / Pages 541-559
Technical Paper / dx.doi.org/10.13182/NSE56-A18467