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Volume 6

Number 3

Enriched Boron-Titanium Dispersions

L. B. Prus, E. S. Byron, F. O. Von Plinsky, S. W. Porembka

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 167-173

Technical Paper / dx.doi.org/10.13182/NSE59-A25656

Blackness Theory and Coefficients for Slab Geometry

C. W. Maynard

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 174-186

Technical Paper / dx.doi.org/10.13182/NSE59-A25657

Nuclear Safety of Iron-Encased Fuel Elements

Norman Ketzlach

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 187-190

Technical Paper / dx.doi.org/10.13182/NSE59-A25658

Perturbation Methods for Reactor Diffusion Equations

Lowell H. Holway, Jr.

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 191-201

Technical Paper / dx.doi.org/10.13182/NSE59-A25659

Uniformly Spaced Control Elements in a Reactor: Theoretical Basis of Application of “Absorption Area” to Reactor Control Evaluation

Lewi Tonks

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 202-213

Technical Paper / dx.doi.org/10.13182/NSE59-A25660

The Elastic Response to Internal Blast Loading of Models of Outer Containment Structures for Nuclear Reactors

J. W. Hanna, W. O. Ewing, Jr. W. E. Baker

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 214-221

Technical Paper / dx.doi.org/10.13182/NSE59-A25661

Some Properties of Uranium-Fissium Alloys

S. T. Zegler M. V. Nevitt

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 222-228

Technical Paper / dx.doi.org/10.13182/NSE59-A25662

Minimum Total Mass

J. Ernest Wilkins, Jr.

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 229-232

Technical Paper / dx.doi.org/10.13182/NSE59-A25663

Determination of Time Behavior of Neutron Density and of Reactivity on the Argonaut Reactor

W. R. Kimel, W. E. Carey, F. G. Prohammer, G. C. Baldwin

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 233-237

Technical Paper / dx.doi.org/10.13182/NSE59-A25664

Analysis of the Coolant Expansion Due to a Loss-of-Coolant Accident in a Pressurized Water, Nuclear Power Plant

Tedric A. Harris

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 238-244

Technical Paper / dx.doi.org/10.13182/NSE59-A25665

Local Pressure Gradients in Forced Convection Vaporization

V. E. Schrock, L. M. Grossman

Nuclear Science and Engineering / Volume 6 / Number 3 / September 1959 / Pages 245-250

Technical Paper / dx.doi.org/10.13182/NSE59-A25666