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Volume 60

Number 3

Exact Doppler Broadening of Tabulated Cross Sections

Dermott E. Cullen, Charles R. Weisbin

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 199-229

Technical Paper / dx.doi.org/10.13182/NSE76-1

Total Neutron Cross Section of Lead

Keiji Kanda, Otohiko Aizawa

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 230-234

Technical Paper / dx.doi.org/10.13182/NSE76-A26879

14.6-MeV Neutron Activation Cross Section for the Xenon Isotopes

R. A. Sigg and P. K. Kuroda

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 235-238

Technical Paper / dx.doi.org/10.13182/NSE76-A26880

Monte Carlo Analysis of Direct Measurements of the Fission Neutron Yield Per Absorption by Uranium-233 and Uranium-235 of Monochromatic Neutrons

J. J. Ullo and M. Goldsmith

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 239-250

Technical Paper / dx.doi.org/10.13182/NSE76-A26881

Monte Carlo Analysis of Thermal-Spectrum Averaged Measurements of η of Uranium-233 and Uranium-235

M. Goldsmith and J. J. Ullo

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 251-261

Technical Paper / dx.doi.org/10.13182/NSE76-A26882

The Effective Delayed Neutron Fraction from Fission in an Unreflected Uranium Sphere from Time Correlation Measurements with Californium-252

J. T. Mihalczo

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 262-275

Technical Paper / dx.doi.org/10.13182/NSE76-4

Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Small Beryllium Assemblies

Suresh Garg, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 276-287

Technical Paper / dx.doi.org/10.13182/NSE76-A26884

Space-Dependent Continuous Neutron Slowing Down Theory Utilizing Integral Transport Concepts

Gilbert Epstein, James Biffer, Martin Becker

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 288-301

Technical Paper / dx.doi.org/10.13182/NSE76-A26885

Transport Equations in Axisymmetric Toroidal Coordinates

Samuel L. Gralnick

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 302-310

Technical Paper / dx.doi.org/10.13182/NSE76-A26886

A Theory of Heat Transfer Between Two Gases in a Mixture

Kalimullah

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 311-314

Technical Note / dx.doi.org/10.13182/NSE76-A26887

The Release of Iodine from Iodide Salts by Gamma Radiolysis

Daniel Cubicciotti, John H. Davies

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 314-319

Technical Note / dx.doi.org/10.13182/NSE76-A26888

Fast-Neutron Excitation of Isomeric States in Indium

Donald L. Smith, James W. Meadows

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 319-322

Technical Note / dx.doi.org/10.13182/NSE76-2

On the Average Energies of β Particles Emitted by Fission Products

M. Goldsmith, K. Shure

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 322-324

Technical Note / dx.doi.org/10.13182/NSE76-A26890

Collision Method in Spherical Geometry by Escape Probabilities

G. Bitelli, A. Turrin

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 324-326

Technical Note / dx.doi.org/10.13182/NSE76-A26891

The Importance of the Uranium-238 Inelastic Transfer Matrix for Fast-Reactor Analysis

T. Choong and E. Kujawski

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 326-329

Technical Note / dx.doi.org/10.13182/NSE76-A26892