Calculation of the Neutron Leakage Spectra and Neutron Doses from Bare Critical Systems
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 239-245
Technical Paper / dx.doi.org/10.13182/NSE61-A25998
Interaction of Separated Fissionable Sysems. Part I
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 246-255
Technical Paper / dx.doi.org/10.13182/NSE61-A25999
Interaction of Separated Fissionable Systems. Part II
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 256-262
Technical Paper / dx.doi.org/10.13182/NSE61-A26000
Determination and Application of the Diffusion Coefficient for Hydrogen in Uranium at 800°C
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 263-266
Technical Paper / dx.doi.org/10.13182/NSE61-A26001
Modified Zirflex Process for Dissolution of 1–10% U-Zr Alloy Fuels in Aqueous NH4F-NH4NO3-H2O2
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 267-273
Technical Paper / dx.doi.org/10.13182/NSE61-A26002
Anion Exchange Separation of Trivalent Actinides and Lanthanides
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 274-277
Technical Paper / dx.doi.org/10.13182/NSE61-A26003
Chemical Feasibility of Nuclear Poisons in Uranium-Thorium Fuel Processing Systems
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 278-284
Technical Paper / dx.doi.org/10.13182/NSE61-A26004
The Solution of Many Region Reactor Kinetics Problems on an Analog Computer
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 285-289
Technical Paper / dx.doi.org/10.13182/NSE61-A26005
The Statistical Aspects of Nuclear Reactor Fuel Element Temperature
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 290-297
Technical Paper / dx.doi.org/10.13182/NSE61-A26006
Total Slow Neutron Cross Section Measurements of Titanium, Zirconium, and Hafnium
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 298-303
Technical Paper / dx.doi.org/10.13182/NSE61-A26007
A Void Measurement Technique for Local Boiling
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 304-311
Technical Paper / dx.doi.org/10.13182/NSE61-A26008
Precision Measurements of the Neutron Total Cross Section of U235
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 312-317
Technical Paper / dx.doi.org/10.13182/NSE61-A26009
Pneumatic Temperature Probes for Gas-Cooled Reactors
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 318-323
Technical Paper / dx.doi.org/10.13182/NSE61-A26010
Irradiated Ra:Be Neutron Sources
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 324-327
Technical Paper / dx.doi.org/10.13182/NSE61-A26011
Method of Studying Xenon Spatial Instability with an Analog Computer
Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 328-337
Technical Paper / dx.doi.org/10.13182/NSE61-A26012