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Volume 67

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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 / Pages 162-171

August 1978

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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 / Pages 172-183

August 1978

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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 / Pages 184-189

August 1978

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Improved Resonance Formulas for Cross Sections of Fissile Elements

M. Segev

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

August 1978

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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 / Pages 235-246

August 1978

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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 / Pages 247-254

August 1978

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Fusion-Fission Analogy and Tnτ Criterion for Fusion Plasmas

J. Rand McNally, Jr.

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

August 1978

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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 / Pages 257-259

August 1978

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The Inverse Problem for a Finite Slab

C. E. Siewert

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

August 1978

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

G. Winkler

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

August 1978

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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 / Pages 263-269

August 1978

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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 / Pages 269-270

August 1978

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Principles of Isotope Geology

Vincent P. Guinn

Nuclear Science and Engineering / Volume 67 / Number 2 / Page 271

August 1978

Nuclear Power Reactor Safety

David Okrent

Nuclear Science and Engineering / Volume 67 / Number 2 / Pages 271-272

August 1978

Heat Transfer and Turbulent Buoyant Convection: Studies and Applications for Natural Environment, Buildings, Engineering Systems

C. J. Hsu

Nuclear Science and Engineering / Volume 67 / Number 2 / Pages 272-273

August 1978

Reactor Neutron Cross Sections for Some (n, ) Reactions

R. S. Tilbury, Henry H. Kramer

Nuclear Science and Engineering / Volume 67 / Number 2 / Page 274

August 1978

Reflectors, Infinite Cylinders, Intersecting Cylinders, and Nuclear Criticality

J. T. Thomas

Nuclear Science and Engineering / Volume 67 / Number 3 / Pages 279-295

September 1978

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Noise Source Estimation of Boiling Water Reactor Power Fluctuation by Autoregression

Kohyu Fukunishi

Nuclear Science and Engineering / Volume 67 / Number 3 / Pages 296-308

September 1978

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A Monte Carlo Biasing Scheme for Adjoint Photon Transport

A. De Matteis, R. Simonini

Nuclear Science and Engineering / Volume 67 / Number 3 / Pages 309-316

September 1978

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