Home / Publications / Journals / Nuclear Science and Engineering / Volume 50 / Number 4

Volume 50

Number 4

Table of Contents
XLACS A Program to Produce Weighted Multigroup Neutron Cross Sections from ENDF/B(N. M. Greene, J. L. Lucius, J. E. White, R. Q. Wright, C. W. Craven, Jr., M. L. Tobias)
An Introduction to On-Line Computers(Melvin Tobias)
Dissociation in Heavy Particle Collisions(Gordon H. Dunn)
Nuclear Power Plant Systems and Equipment(M. J. Larocco)

Neutron-Induced Gamma-Ray Production in Iron for the Energy Range 0.8 ≤ E_n ≤ 20 MeV

J. K. Dickens, G. L. Morgan, F. G. Perey

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 311-336

Technical Paper / dx.doi.org/10.13182/NSE73-A26567

Neutron Thermalization in Various H₂O-D₂O Mixtures in the Temperature Range 253 to 4°K

G. S. Gangwani, S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 337-344

Technical Paper / dx.doi.org/10.13182/NSE73-A26568

Adjustment of Multigroup Neutron Cross Sections by a Correlation Method

M. Salvatores

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 345-353

Technical Paper / dx.doi.org/10.13182/NSE73-A26569

A Many-Resonance Approximation for the Neutron Energy Spectrum

M. Segev

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 354-363

Technical Paper / dx.doi.org/10.13182/NSE73-A26570

Thermal-Neutron Capture Cross Sections and Capture Resonance Integrals of Americium-241

R. M. Harbour, K. W. MacMurdo, F. J. McCrosson

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 364-369

Technical Paper / dx.doi.org/10.13182/NSE73-A26571

Stability of Nuclear Reactors with Changes in Eigenvalue

Dong H. Nguyen

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 370-381

Technical Paper / dx.doi.org/10.13182/NSE73-A26572

Two-Phase Mixing for Annular Flow in Simulated Rod Bundle Geometries

Kuldip Singh, C. C. St. Pierre

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 382-387

Technical Note / dx.doi.org/10.13182/NSE73-A26573

Extrapolated Endpoint for the Uniform Source Half-Space Problem

W. P. Petrick, C. T. McDaniel, A. Leonard

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 388-390

Technical Note / dx.doi.org/10.13182/NSE73-A26574

Interpolation of Tabular Secondary Neutron and Photon Energy Distributions

Richard J. Doyas, Sterrett T. Perkins

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 390-392

Technical Note / dx.doi.org/10.13182/NSE73-A26575

The (n, γn’) Reaction in Calculations of Fast Reactor Neutron Spectra

M. P. Fricke, J. M. Neill

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 392-397

Technical Note / dx.doi.org/10.13182/NSE73-A26576

Effect of the ²³⁸U(n, γn’) Reaction in Fast-Neutron Spectrum Critical Assemblies

Harry H. Hummel, Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 397-398

Technical Note / dx.doi.org/10.13182/NSE73-A26577

Exact Time-Dependent Second Spatial Moment of the One-Speed Neutron Transport Model

C. S. Barnett

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 398-401

Technical Note / dx.doi.org/10.13182/NSE73-A26578