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Volume 3

Number 1

Table of Contents
The Doppler Coefficient of U²³⁵ Fuel Elements(MONTE V. DAVIS)
The Magneto-Ionic Expander Isotope Separator Applied to Uranium(JOSEPH SLEPIAN)
Foil Depression Factors for Indium Disk Detectors(TOM L. GALLAGHER)

The Thermal Neutron Spectrum in a Diffusing Medium

H. Hurwitz, Jr.; M.S. Nelkin

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE58-A25440

Fast Neutron Scattering from Thick Slabs

T. D. Strickler, H. E. Gilbert, J. A. Auxier

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 11-18

Technical Paper / dx.doi.org/10.13182/NSE58-A25441

Effects of Irradiation on Corrosion Resistance of Some High Uranium Alloys

Sherman Greenberg, Joseph E. Draley

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 19-28

Technical Paper / dx.doi.org/10.13182/NSE58-A25442

Some Characteristics of the Thermal Neutron Scattering Probability

R. K. Osborn

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 29-37

Technical Paper / dx.doi.org/10.13182/NSE58-A25443

Estimation of Charge Life for Reactors with Small Cores

H. L. McMurray, A. V. Grimaud, G. H. Hanson

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 38-46

Technical Paper / dx.doi.org/10.13182/NSE58-A25444

The Decay of Fission Product Activity for Cyclic Operation of a Reactor

James W. Butler, M. Grotenhuis

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 47-51

Technical Paper / dx.doi.org/10.13182/NSE58-A25445

The Application of Reactor Kinetics to the Analysis of Experiments

A. F. Henry

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 52-70

Technical Paper / dx.doi.org/10.13182/NSE58-1

Neutron Self-Shielding in a Simple Plane Lattice

Joel Bengston

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 71-76

Technical Paper / dx.doi.org/10.13182/NSE58-A25447

A Semiempirical Method of Calculating the Energy Absorption Buildup Factor with an Application to a Uniformly Contaminated Space Having Spherical Boundaries

Keran O'Brien, Wayne M. Lowder, Leonard R. Solon

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 77-84

Technical Paper / dx.doi.org/10.13182/NSE58-A25448

Heat Transfer In Heterogeneous Circulating-Fuel Reactors

H. F. Poppendiek, L. D. Palmer

Nuclear Science and Engineering / Volume 3 / Number 1 / January 1958 / Pages 85-106

Technical Paper / dx.doi.org/10.13182/NSE58-A25449

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