Volume 12

Number 3

Table of Contents
Spatial Dependence of Thermal-Neutron Spectra and the Interpretation of Thermal Utilization Measurements(R. Sher, H. Kouts)
Re: “Spatial Dependence of Thermal-Neutron Spectra and the Interpretation of Thermal Utilization Measurements”(Robert W. Deutsch)
A Note on the Measurement of Diffusion Parameters by the Pulsed-Neutron Source Technique(G. DeSaussure)
The Resonance Integral For Uranium Metal and Oxide(E. Hellstrand, G. Lundgren)
The Temperature Dependence of the Viscosity of Liquid Metals(Simon W. Strauss)
Measured Slowing Down Distribution at the Indium Resonance from a Line Source of Fission Neutrons in Heavy Water(W. E. Graves)
Radioisotope Applications Engineering(John P. Danforth)
Nuclear Radiation Measurement(W. W. Managan)
KARE(J. A. Archibald, Jr., E. D. Reilly, Jr.)
FLEER(J. L. Fletcher, J. P. Jewett, E. D. Reilly, Jr.)
TRAM(R. A. Pfeiffer, W. W. Stone)
Los Alamos Least Squares(Roger H. Moore)
9-RENUPAK (UNC-90-1)(J. Certaine, E. DeDufour, G. Rabinowitz)
9-NIOBE (UNC-90-2)(Stanley Preiser)

Kinetics of Structural Changes during Beta Transformation of Uranium

William R. McDonell

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 325-336

Technical Paper / dx.doi.org/10.13182/NSE62-A28082

Boron Trifluoride as a Soluble Poison in Molten Salt Reactor Fuels

J. H. Shaffer, W. R. Grimes, and G. M. Watson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 337-340

Technical Paper / dx.doi.org/10.13182/NSE62-A28083

Experimental Bucklings of Heavy Water Moderated Lattices of Natural Uranium Metal Rod Clusters

T. J. Hurley, Jr., H. R. Fike, and G. F. O'Neill

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 341-347

Technical Paper / dx.doi.org/10.13182/NSE62-A28084

Exponential Measurements of Natural Uranium Rods in Heavy Water and Comparisons with Critical Experiments

E. C. Wingfield and E. J. Hennelly

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 348-358

Technical Paper / dx.doi.org/10.13182/NSE62-A28085

Determination of Eta by Comparison of for U²³³ and Pu²³⁹ with for U²³⁵ in a Flux Trap Critical Assembly

R. Gwin, D. W. Magnuson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 359-363

Technical Paper / dx.doi.org/10.13182/NSE62-A28086

The Measurement of Eta and Other Nuclear Properties of U²³³ and U²³⁵ in Critical Aqueous Solutions

R. Gwin, D. W. Magnuson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 364-380

Technical Paper / dx.doi.org/10.13182/NSE62-A28087

Multichannel Flux Synthesis

E. L. Wachspress, R. D. Burgess, S. Baron

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 381-389

Technical Paper / dx.doi.org/10.13182/NSE62-A28088

An Analysis of Vapor Void Profiles in Heated Channels

Gerald Houghton

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 390-397

Technical Paper / dx.doi.org/10.13182/NSE62-A28089

Engineering Considerations for Remote Refabrication of EBR-II Fuel Elements

A. B. Shuck, J. E. Ayer

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 398-404

Technical Paper / dx.doi.org/10.13182/NSE62-A28090

Equipment for Remote Injection Casting of EBR-II Fuel

H. F. Jelinek, G. M. Iverson

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 405-411

Technical Paper / dx.doi.org/10.13182/NSE62-A28091

Equipment for the Remote Demolding, Sizing, and Inspection of EBR-II Cast Fuel Pins

N. J. Carson, Jr., S. B. Brak

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 412-418

Technical Paper / dx.doi.org/10.13182/NSE62-A28092

Leak Testing of EBR-II Fuel Rods

A. P. Grunwald

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 419-423

Technical Paper / dx.doi.org/10.13182/NSE62-A28093

Assembling, Sodium Bonding, and Bond Testing of EBR-II Fuel Rods

T. C. Cameron, N. F. Hessler

Nuclear Science and Engineering / Volume 12 / Number 3 / March 1962 / Pages 424-431

Technical Paper / dx.doi.org/10.13182/NSE62-A28094