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Volume 11

Number 3

Calculation of the Neutron Leakage Spectra and Neutron Doses from Bare Critical Systems

J. R. Knight

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

Floro Miraldi, Melville Clark, Jr.

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

Floro Miraldi, Melville Clark, Jr.

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

C. J. Oblinger, H. A. Dube

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

T. A. Gens, R. E. Blanco

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

M. H. Lloyd, R. E. Leuze

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

J. G. Moore, R. H. Rainey

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

C. N. Kelber, L. C. Just, N. F. Morehouse, Jr.

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

Frederick H. Abernathy

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

E. G. Joki, J. E. Evans, R. R. Smith

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

H. C. Perkins, Jr., M. Yusuf, G. Leppert

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

A. Saplakoglu

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

Lester L. Kintner, Donald A. Lampe, Aikman Armstrong

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

D. J. Dudziak, L. B. Freeman

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

R. M. Pearce

Nuclear Science and Engineering / Volume 11 / Number 3 / November 1961 / Pages 328-337

Technical Paper / dx.doi.org/10.13182/NSE61-A26012