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Home / Publications / Journals / Nuclear Science and Engineering / Volume 20 / Number 1

Volume 20

Number 1

Table of Contents
A Theorem Concerning the Slowing-Down Equation(M. W. Dyos)
Swelling of Irradiated Uranium-Zirconium Alloys on Annealing(B. A. Loomis)
A Generalization of the Endpoint Method(K. O. Thielheim)
System Analysis of Nuclear Reactor Dynamics(George G. Biro)
The Technology of the Treatment of Uranium Concentrates(Albert A. Jonke)
Heavy Water Lattices(Charles N. Kelber)

Fatigue Design Basis for Zircaloy Components

W. J. O'Donnell, B. F. Langer

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE64-A19269

Processing of Graphite Reactor Fuels Containing Coated Particles and Ceramics

R. E. Blanco, G. I. Cathers, L. M. Ferris, T. A. Gens, R. W. Horton, E. L. Nicholson

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 13-22

Technical Paper / dx.doi.org/10.13182/NSE64-A19270

A New Liquid Scintillator for Thermal Neutron Detection

H. H. Ross, R. E. Yerick

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 23-27

Technical Paper / dx.doi.org/10.13182/NSE64-A19271

Laminar, Turbulent, and Transition Gas Flow in Porous Media

E. Creutz

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 28-44

Technical Paper / dx.doi.org/10.13182/NSE64-A19272

Thermally Induced Vibrations of Concentric Thin Spherical Shells

Arthur L. Austin

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 45-52

Technical Paper / dx.doi.org/10.13182/NSE64-A19273

Spatial-Distribution Functions for Calculating Neutron Densities by Monte Carlo

Harvey J. Amster, Wilson K. Talley

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 53-59

Technical Paper / dx.doi.org/10.13182/NSE64-A19274

Prompt-Neutron Lifetime in Critical Enriched-Uranium Metal Cylinders and Annuli

John T. Mihalczo

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 60-65

Technical Paper / dx.doi.org/10.13182/NSE20-60

Point-to-Point Kernel Analysis of an Experiment to Determine Wall Penetration of a Squarebased Concrete Structure by Gamma Radiation

R. E. Rexroad, M. A. Schmoke H. J. Tiller, A. Foderaro, L. Degelman, G. Kowal

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 66-79

Technical Paper / dx.doi.org/10.13182/NSE64-A19276

Ratio of Capture to Fission in U²³⁵ at keV Neutron Energies

L. W. Weston, G. de Saussure, R. Gwin

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 80-87

Technical Paper / dx.doi.org/10.13182/NSE64-A19277

The Milne Problem in a Finite Domain I: Isotropic Scattering

F. A. Hinchey, E. A. Dean, J. B. Pearce

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 88-92

Technical Paper / dx.doi.org/10.13182/NSE64-A19278

Transport-Theory Calculations of Temperature Coefficients in Heterogeneous Reactor Lattices

John E. Suich, Henry C. Honeck

Nuclear Science and Engineering / Volume 20 / Number 1 / September 1964 / Pages 93-110

Technical Paper / dx.doi.org/10.13182/NSE64-A19279

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