ANS / Publications / Journals / Nuclear Science and Engineering

Solution of the One-Velocity Transport Equation in Terms of Synthetic Kernels

Herbert Henryson, II, David S. Selengut

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 1-18

Technical Paper / dx.doi.org/10.13182/NSE69-A20894

A Stability Criterion for Space-Dependent Nuclear-Reactor Systems with Variable Temperature Feedback

William E. Kastenberg

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 19-29

Technical Paper / dx.doi.org/10.13182/NSE69-A20895

The Metastatic Method in Nuclear Reactor Core Kinetics Calculations

A. Galati

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 30-40

Technical Paper / dx.doi.org/10.13182/NSE69-A20896

A Discrete Stochastic Model for Neutron Moderation

T. J. Williamson, R. W. Albrecht

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 41-58

Technical Paper / dx.doi.org/10.13182/NSE69-A20897

Numerical Results of Interfacial Effects on Neutron Waves

O. C. Baldonado, R. C. Erdmann

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 59-65

Technical Paper / dx.doi.org/10.13182/NSE69-A20898

The Temperature Dependence of Epithermal Neutron Capture and Fission in Uranium-235 Dioxide

F. C. Schoenig, Jr., F. A. White, F. Feiner

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 66-84

Technical Paper / dx.doi.org/10.13182/NSE69-A20899

A Theory of Pulsed Neutron Experiments in Polycrystalline Media

Robert Conn, Noel Corngold

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 85-93

Technical Paper / dx.doi.org/10.13182/NSE69-A20900

Analysis of Pulsed Neutron Experiments in Polycrystalline Media Using a Model Kernel

Robert Conn, Noel Corngold

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 94-103

Technical Paper / dx.doi.org/10.13182/NSE69-A20901

Time-Dependent Analysis of Subcritical and Nonmultiplying Systems

P. d'Oultremont

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 104-110

Technical Paper / dx.doi.org/10.13182/NSE69-A20902

Fast Neutron Spectrum for a Subcritical Section of a Homogeneous ²³⁵U-Polyethylene Critical Assembly

S. C. Cohen, R. A. Moore, J. C. Young, J. L. Russell, Jr.

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 111-126

Technical Paper / dx.doi.org/10.13182/NSE69-A20903

Thermal-Neutron Diffusion in Aqueous Absorbing Solutions

A. J. H. Goddard, P. W. Johnson

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 127-136

Technical Paper / dx.doi.org/10.13182/NSE69-A20904

Neutron Radiative Capture and Transmission Measurements of W and Zr Isotopes in the keV Region

Z. M. Bartolome, R. W. Hockenbury, W. R. Moyer, J. R. Tatarczuk, R. C. Block

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 137-156

Technical Paper / dx.doi.org/10.13182/NSE69-A20905

Prediction of Tube Wall Temperatures with Axial Variation of Heating Rate and Gas Property Variation

C. A. Bankston, D. M. McEligot

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 157-162

Technical Paper / dx.doi.org/10.13182/NSE69-A20906

Reactor Control Using a New Multivariable Design Technique

Charles R. Slivinsky, Lynn E. Weaver

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 163-166

Technical Note / dx.doi.org/10.13182/NSE69-A20907

Escape Probabilities in Close-Packed Lattices

R. S. Carlsmith, D. Steiner

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 166-167

Technical Note / dx.doi.org/10.13182/NSE69-A20908

The Thermal Neutron Diffusion Length in Liquid Terphenyl

A. J. H. Goddard, G. E. B. Tremeer

Nuclear Science and Engineering / Volume 37 / Number 1 / July 1969 / Pages 167-169

Technical Note / dx.doi.org/10.13182/NSE69-A20909