Home / Publications / Journals / Nuclear Science and Engineering / Volume 54 / Number 2

Volume 54

Number 2

Table of Contents
A Mechanism for UO₂/Sodium Thermal Interactions(S. J. Board)
Irradiation Effects in Fissile Materials.(Mark T. Robinson)

Relativistic Compton Scattering by the Discrete Ordinates Method

Brian G. Stephan, Charles J. Bridgman

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 101-115

Technical Paper / dx.doi.org/10.13182/NSE74-A23399

Single-Level Analysis of the Uranium-233 Fission Cross Section for Neutron Energies Between 6 and 124 eV

S. Nizamuddin, J. Blons

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 116-126

Technical Paper / dx.doi.org/10.13182/NSE74-A23400

Neutron Pulses Slowing Down in Heavy Media Analysis with Applications of the Lead Spectrometer

Mohamed Sawan, Robert W. Conn

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 127-142

Technical Paper / dx.doi.org/10.13182/NSE74-A23401

Correcting for Emission-Time Effects in Neutron Time-of-Flight Data Using Multiple Time Spectra

H. A. Robitaille, J. S. Hewitt

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 143-156

Technical Paper / dx.doi.org/10.13182/NSE74-A23402

Estimation of Reactivity Worths by Local Calculation

M. J. Lineberry

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 157-165

Technical Paper / dx.doi.org/10.13182/NSE74-A23403

Minimal Time Control of Spatial Xenon Oscillations in Nuclear Power Reactors

A. A. El-Bassioni, C. G. Poncelet

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 166-176

Technical Paper / dx.doi.org/10.13182/NSE74-A23404

Calculation of the Decay Power of Fission Products

Kanji Tasaka, Nobuo Sasamoto

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 177-189

Technical Paper / dx.doi.org/10.13182/NSE74-A23405

Cross Section for the Delayed-Neutron Yield from the ⁹Be(n, p) ⁹Li Reaction at Neutron Energies of 14.5 and 14.9 MeV

R. H. Augustson, H. O. Menlove

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 190-191

Technical Note / dx.doi.org/10.13182/NSE74-A23406

Neutron-Induced Gamma-Ray Production in Titanium for Incident-Neutron Energies of 4.9, 5.4, and 5.9 MeV

J. K. Dickens

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 191-196

Technical Note / dx.doi.org/10.13182/NSE74-A23407

Functionals to Represent the Neutron Flux in Fast Pulsed Assemblies

Harold N. Knickle, Paul B. Daitch

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 196-200

Technical Note / dx.doi.org/10.13182/NSE74-A23408

Flux Synthesis Calculations for Fast Reactors

C. H. Adams, W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 201-206

Technical Note / dx.doi.org/10.13182/NSE74-A23409

Application of an Improved Time-Difference Method for Spatial Xenon Transient Analysis

John C. Lee

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 206-214

Technical Note / dx.doi.org/10.13182/NSE74-A23410

Critical Heat Flux and Pressure Drop Tests with Parallel Upflow of High Pressure Water in Bundles of Twenty ¾-in. Rods

B. W. LeTourneau, M. E. Gavin, S. J. Green

Nuclear Science and Engineering / Volume 54 / Number 2 / June 1974 / Pages 214-232

Technical Note / dx.doi.org/10.13182/NSE74-A23411