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Volume 8

Number 5

Investigation of Natural Convection Heat Transfer in Liquid Sodium

John S. McDonald, T. J. Connolly

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 369-377

Technical Paper / dx.doi.org/10.13182/NSE60-A25816

Reactor Neutron Activation Cross Sections for a Number of Elements

W. S. Lyon

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 378-380

Technical Paper / dx.doi.org/10.13182/NSE60-A25817

Water-Moderated Cores with Boron Steel Septa at Elevated Temperatures

G. D. Hickman, J. A. Bistline, L. A. MacNaughton

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 381-392

Technical Paper / dx.doi.org/10.13182/NSE60-A25818

Competitive Extinction in Neutron Monochromating Crystals

R. R. Spencer, J. R. Smith

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 393-399

Technical Paper / dx.doi.org/10.13182/NSE60-A25819

A Few-Group Theory of Water Gap Peaking

Gerald P. Calame

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 400-404

Technical Paper / dx.doi.org/10.13182/NSE60-A25820

Measurements of Pu and U235 Fission Rates in Water—Uranium Reactor Spectra

D. Klein

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 405-409

Technical Paper / dx.doi.org/10.13182/NSE60-A25821

A Nondestructive Assay Device for Highly Enriched Fuel Assemblies

Richard V. Babcock, Stanley L. Ruby

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 410-415

Technical Paper / dx.doi.org/10.13182/NSE60-A25822

An Experimental Study of the Relative U235 Fission Activation as a Function of Energy in Slightly Enriched Uranium-Water Lattices

John J. Volpe, D. Klein

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 416-425

Technical Paper / dx.doi.org/10.13182/NSE60-A25823

Thermal Neutron Flux Distributions in Space and Energy

Paul Michael

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 426-431

Technical Paper / dx.doi.org/10.13182/NSE60-A25824

Recovery of Uranium and Thorium from Graphite Fuel Elements. I. Grind-Leach Process

Mildred J. Bradley, Leslie M. Ferris

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 432-436

Technical Paper / dx.doi.org/10.13182/NSE60-A25825

Integral Reactor Theory: Orthogonality and Importance

M. A. Robkin, M. Clark, Jr.

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 437-442

Technical Paper / dx.doi.org/10.13182/NSE60-A25826

The Measurement of Reactivity

Cesar A. Sastre

Nuclear Science and Engineering / Volume 8 / Number 5 / November 1960 / Pages 443-447

Technical Paper / dx.doi.org/10.13182/NSE60-A25827