Home / Publications / Journals / Nuclear Science and Engineering / Volume 67 / Number 2

Volume 67

Number 2

Table of Contents
Principles of Isotope Geology(Vincent P. Guinn)
Nuclear Power Reactor Safety(David Okrent)
Heat Transfer and Turbulent Buoyant Convection: Studies and Applications for Natural Environment, Buildings, Engineering Systems(C. J. Hsu)
Reactor Neutron Cross Sections for Some (n, ã) Reactions(R. S. Tilbury, Henry H. Kramer)

Spectrum of the Multigroup-Multipoint Diffusion Operator with Delayed Neutrons

J. Devooght

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 147-161

Technical Paper / dx.doi.org/10.13182/NSE78-A15432

The Application of the Symmetric SOR and the Symmetric SIP Methods for the Numerical Solution of the Neutron Diffusion Equation

H. H. Wang

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 162-171

Technical Paper / dx.doi.org/10.13182/NSE78-A15433

Spatial Distribution Measurements of Fission Neutrons in Water as an Oxygen Data Test

L. Green, J. J. Ullo

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 172-183

Technical Paper / dx.doi.org/10.13182/NSE78-A15434

A Measurement of the Total Neutron Cross Section of Iron-58 in the Energy Range from 7 to 325 keV

H. Beer, Ly Di Hong, F. Käppeler

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 184-189

Technical Paper / dx.doi.org/10.13182/NSE78-A15435

Unified Absolute Differential Cross Sections for Neutron Production by the Hydrogen Isotopes for Charged-Particle Energies Between 6 and 17 MeV

M. Drosg

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 190-220

Technical Paper / dx.doi.org/10.13182/NSE67-190

Improved Resonance Formulas for Cross Sections of Fissile Elements

M. Segev

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 221-234

Technical Paper / dx.doi.org/10.13182/NSE78-A15437

A Computational Study of the Density and Temperature Distribution in a Freely Expanding Uranium Hexafluoride Gas

H. Mikami

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 235-246

Technical Paper / dx.doi.org/10.13182/NSE78-A15438

A Calculation Model for Predicting Concentrations of Radioactive Corrosion Products in the Primary Coolant of Boiling Water Reactors

Shunsuke Uchida, Makoto Kikuchi, Yamato Asakura, Hideo Yusa, Katsumi Ohsumi

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 247-254

Technical Paper / dx.doi.org/10.13182/NSE78-A15439

Fusion-Fission Analogy and Tnτ Criterion for Fusion Plasmas

J. Rand McNally, Jr.

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 255-257

Technical Note / dx.doi.org/10.13182/NSE78-A15440

Benchmark Calculations for a Sodium-Cooled Breeder Reactor by Two- and Three-Dimensional Diffusion Methods—II

G. Buckel, K. Küfner, B. Stehle

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 257-259

Technical Note / dx.doi.org/10.13182/NSE78-A15441

The Inverse Problem for a Finite Slab

C. E. Siewert

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 259-260

Technical Note / dx.doi.org/10.13182/NSE78-A15442

Precise Measurement of the ⁶³Cu(n,α)⁶⁰Co Cross Section with 14-MeV Neutrons

G. Winkler

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 260-263

Technical Note / dx.doi.org/10.13182/NSE78-A15443

A Quantitative Comparison of Solidification Analysis for Single-Component and Mixed-Oxide Fuels

Timothy D. Welch, August W. Cronenberg

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 263-269

Technical Note / dx.doi.org/10.13182/NSE78-A15444

The Volume Adsorption Capacity of 0.98 mol% Argon on Activated Carbon at 20°C

R. Madey, P. J. Photinos, K. B. Lee

Nuclear Science and Engineering / Volume 67 / Number 2 / August 1978 / Pages 269-270

Technical Note / dx.doi.org/10.13182/NSE78-A15445