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Volume 32

Number 1

A Two-Dimensional Turbulent-Flow Mixing Model for Parallel-Flow Rod Bundles

Phillip A. Lowe

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE68-A18817

In-Pile Heat-Transfer Studies of Roughened Helium-Cooled Reactor Fuel Elements

C. A. Brandon, G. J. Kidd, Jr.

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 8-15

Technical Paper / dx.doi.org/10.13182/NSE68-A18818

The Influence of Axial Conduction on the Thermal Entry-Region Heat Transfer in Magnetohydrodynamic Channel Flow

Chia-Jung Hsu, George C. Lindauer

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 16-29

Technical Paper / dx.doi.org/10.13182/NSE68-A18819

Fission-Spectrum-Averaged Cross-Section Measurement for the 9Be (n, 2n) Reaction

L. Green

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 30-34

Technical Paper / dx.doi.org/10.13182/NSE68-A18820

Selected Fission Cross Sections for 232Th, 233U, 234U, 235U, 236U, 237Np, 238U, 239Pu, 240Pu, 241Pu, and 242Pu

William G. Davey

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 35-45

Technical Paper / dx.doi.org/10.13182/NSE68-A18821

Half-Lives of Radionuclides—III

S. A. Reynolds, J. F. Emery, E. I. Wyatt

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 46-48

Technical Paper / dx.doi.org/10.13182/NSE68-A18822

The Measurement of Short-Lived Delayed Photoneutrons from Fission-Fragment Gamma Rays of 235U in Heavy Water

R. J. Onega, P. W. Forbes, A. K. Furr, A. Robeson

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 49-55

Technical Paper / dx.doi.org/10.13182/NSE68-A18823

The Validity of the Straightahead Approximation in Space-Vehicle Shielding Studies—Part II

R. G. Alsmiller, Jr., D. C. Irving, H. S. Moran

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 56-61

Technical Paper / dx.doi.org/10.13182/NSE68-A18824

A Method for the Calculation of Neutron-Capture Gamma-Ray Spectra

K. J. Yost

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 62-75

Technical Paper / dx.doi.org/10.13182/NSE68-A18825

Mathematical Verification of a Certain Monte Carlo Sampling Technique and Applications of the Technique to Radiation Transport Problems

W. A. Coleman

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 76-81

Technical Paper / dx.doi.org/10.13182/NSE68-1

A New Synthesis Method for Pulsed-Neutron Experiments

J. Devooght, C. Machgeels

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 82-92

Technical Paper / dx.doi.org/10.13182/NSE68-A18827

Excitation of Higher Space Modes in Reactor Transfer Function Measurement (Part I)

Genn Saji

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 93-100

Technical Paper / dx.doi.org/10.13182/NSE68-A18828

Extensions of Asymptotic Neutron Diffusion Theory

Alan M. Winslow

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 101-110

Technical Paper / dx.doi.org/10.13182/NSE68-A18829

An Exact Solution of Milne's Problem with a General Scattering Law

T. Trombetti

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 111-119

Technical Paper / dx.doi.org/10.13182/NSE68-A18830

Biorthogonal Angular Polynomial Expansion of the Two-Dimensional Transport Equation

K. D. Lathrop, N. S. Demuth

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 120-130

Technical Paper / dx.doi.org/10.13182/NSE68-A18831

Average Cross Sections and Resonance Integrals of 242mAm

S. T. Perkins, G. F. Auchampaugh, R. W. Hoff, C. D. Bowman

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 131-132

Technical Note / dx.doi.org/10.13182/NSE68-A18832

Half-Life of 54Mn

W. H. Zimmer, R. E. Dahl

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 132-133

Technical Note / dx.doi.org/10.13182/NSE68-A18833

Minimum Thickness of a Water-Reflected Infinite Slab of an Aqueous Solution of 235UO2F2 at Optimum Concentration

J. Wallace Webster

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 133-135

Technical Note / dx.doi.org/10.13182/NSE68-A18834

Minimum Critical 235U Enrichment of Homogeneous, Hydrogenous Uranyl Nitrate Systems

S. R. Bierman, G. M. Hess

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 135-139

Technical Note / dx.doi.org/10.13182/NSE68-A18835

Energy Correlation in a Moderating Nonmultiplying Medium

W. J. Turner

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 139-140

Technical Note / dx.doi.org/10.13182/NSE68-A18836

One-Velocity Calculations for the Analysis of Reactor Physics Experiments

P. d'Oultremont, M. Van Malder

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 140-142

Technical Note / dx.doi.org/10.13182/NSE68-A18837

Reactor Noise Measurements Using Gamma Rays

Wayne K. Lehto, John M. Carpenter

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 142-146

Technical Note / dx.doi.org/10.13182/NSE68-A18838

An Optimal Control of a Distributed-Parameter Reactor

Sang Hyon Kyong

Nuclear Science and Engineering / Volume 32 / Number 1 / April 1968 / Pages 146-149

Technical Note / dx.doi.org/10.13182/NSE68-A18839