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Volume 31

Number 2

Study of Lithium Mobility in Irradiated Silicon

Walter A. Hackler, Chihiro Kikuchi

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 175-182

Technical Paper / dx.doi.org/10.13182/NSE68-A18229

Geometry and Barrier Attenuation of Cobalt-60 Gamma Rays by a Vertical Steel Slab

G. E. Plummer

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 183-190

Technical Paper / dx.doi.org/10.13182/NSE68-A18230

A Study of Fission-Neutron Spectra with High-Energy Activation Detectors. Part II: Fission Spectra

James A. Grundl

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 191-206

Technical Paper / dx.doi.org/10.13182/NSE68-A18231

The Energy Spectrum of Fast Neutrons Slowing Down from a Fission Source in a Homogeneous Medium

T. E. Murley, I. Kaplan

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 207-214

Technical Paper / dx.doi.org/10.13182/NSE68-A18232

Cross-Spectral Density Measurements in a Coupled-Core Reactor

Richard A. Hendrickson, Glenn Murphy

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 215-221

Technical Paper / dx.doi.org/10.13182/NSE68-A18233

Analysis of Pulsed Fast-Neutron Spectra in Multiplying Assemblies

J. D. Jenkins, P. B. Daitch

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 222-233

Technical Paper / dx.doi.org/10.13182/NSE68-A18234

The Statistical Estimation of Thermal-Neutron Cross Sections

J. L. Cook, A. L. Wall

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 234-240

Technical Paper / dx.doi.org/10.13182/NSE68-A18235

Measurement of 135I Yield Ratios and Fission-Product Cross Sections in the Advanced Reactivity Measurement Facilities

R. G. Nisle, I. E. Stepan

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 241-246

Technical Paper / dx.doi.org/10.13182/NSE68-A18236

Low-Flux Measurement of 235U Epicadmium Capture-to-Fission Ratio

W. C. Redman, M. M. Bretscher

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 247-253

Technical Paper / dx.doi.org/10.13182/NSE68-A18237

Neutron Scattering from Light Water

J. R. Beyster

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 254-271

Technical Paper / dx.doi.org/10.13182/NSE68-A18238

Energy Optimal Xenon Shutdown

Jeffrey Lewins, Gordon R. Woodcock, Theodore J. Williamson, Albert L. Babb

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 272-281

Technical Paper / dx.doi.org/10.13182/NSE68-A18239

Monte Carlo Analysis of Nuclear Reactor Fluctuation Models

Burt A. Zolotar

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 282-294

Technical Paper / dx.doi.org/10.13182/NSE68-A18240

Monoenergetic Critical Parameters and Decay Constants for Small Homogeneous Spheres and Thin Homogeneous Slabs

I. Carlvik

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 295-303

Technical Paper / dx.doi.org/10.13182/NSE31-295

Numerical Solution of the Time-Dependent Multigroup Diffusion Equations

J. Barclay Andrews, II, K. F. Hansen

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 304-313

Technical Paper / dx.doi.org/10.13182/NSE68-A18242

Comparison of Neutron-Transport and Diffusion Theories of Isotropic Scattering

P. S. Grover, L. S. Kothari, A. K. Ghatak

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 314-317

Technical Paper / dx.doi.org/10.13182/NSE68-A18243

Accuracy of Transport Theory Calculations of an Anisotropic Neutron Flux

Pekka Jauho, Heikki Kalli

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 318-324

Technical Paper / dx.doi.org/10.13182/NSE68-A18244

A Strategy for the Application of Space-Angle Synthesis to Practical Problems in Neutron Transport

M. Natelson

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 325-336

Technical Paper / dx.doi.org/10.13182/NSE68-A18245

Effect of Property Variation on the Turbulent Flow of Gases in Tubes: The Thermal Entry

P. M. Magee, D. M. McEligot

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 337-341

Technical Note / dx.doi.org/10.13182/NSE68-A18246

Total Cross Sections of Na, K, and Ca for 14-MeV Neutrons

F. Guarrini, A. Luches, G. Pauli, G. Poiani

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 341-343

Technical Note / dx.doi.org/10.13182/NSE68-A18247

Absolute Neutron Yields from Thick Target NATC(α,n)

R. L. Macklin, J. H. Gibbons

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Page 343

Technical Note / dx.doi.org/10.13182/NSE68-A18248

Comparison of Beryllium Photoneutron Decay Sets Using Experimental SNAP Data

Eric H. Ottewitte

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 343-346

Technical Note / dx.doi.org/10.13182/NSE68-A18249

Suggested Procedures for Utilizing MUFT Resonance Parameters to Include Doppler Broadening

David T. Goldman

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 346-349

Technical Note / dx.doi.org/10.13182/NSE68-A18250

The Application of Synthesis Techniques to the Calculations of Three-Dimensional Reactivity-Coefficient Distributions

J. L. Bear, F. D. Judge, E. R. Venerus

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 349-353

Technical Note / dx.doi.org/10.13182/NSE68-A18251

Anomalies Arising from the Use of Adjoint Weighting in a Collapsed Group-Space Synthesis Model

J. B. Yasinsky, S. Kaplan

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 354-358

Technical Note / dx.doi.org/10.13182/NSE68-A18252

Flux Tilting in a Two-Zone Reactor

D. E. Jeffers, K. Hall

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 358-359

Technical Note / dx.doi.org/10.13182/NSE68-A18253