Volume 8

Number 3

Table of Contents
Characteristics of a Continuous “On-Stream” Analysis System Using a Multikilocurie ¹²⁴Sb_Be Neutron Source
A Practical Approach to Nuclear Criticality Safety
Lanthanide / Actinide Chemistry(Burris B. Cunningham)
Molecular Processes on Solid Surfaces(Donald E. O'Reilly)
Statistical Models in Engineering(Neil Cox)

Measurement of Control Schemes for Fast-Spectrum Compact Reactors

J. F. Kunze, F. L. Sims, J. M. Byrne, R. E. Reid

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 226-239

Paper / Reactor / dx.doi.org/10.13182/NT70-A28669

N-Reactor-WPPSS Complex Operating Performance

Emil E. Leitz

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 240-245

Paper / Reactor / dx.doi.org/10.13182/NT70-A28670

The Measurement of Radial Power Distributions in a Triga Fuel Element during Reactor Power Excursions

W. A. Goodwin, M. E. Wyman

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 246-254

Paper / Reactor / dx.doi.org/10.13182/NT70-A28671

An Experimental Analysis Of Fission-Gas Holdup Beds

Dwight W. Underhill

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 255-260

Paper / Fuel / dx.doi.org/10.13182/NT70-A28672

Stationary Gas Bubbles in Narrow Liquid-Filled Gaps

H. O. Schad, A. A. Bishop

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 261-275

Paper / Fuel / dx.doi.org/10.13182/NT70-A28673

Well-Logging Research for Geonuclear Technology

J. R. Hearst, R. C. Carlson

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 276-282

Paper / Nuclear Explosive / dx.doi.org/10.13182/NT70-A28674

Void-Space Analysis by Use of Thermal-Neutron Analysis Irradiated Air (⁴¹Ar)

Jerry B. F. Champlin

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 283-289

Paper / Analysis / dx.doi.org/10.13182/NT70-A28675

Application of Neutron Activation Analysis to the Sweat Test Diagnosis of Cystic Fibrosis

Robert G. McAndrew, James B. Smathers, , Richard E. Wainerdi, G. M. Harrison, Robert Doggett

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 290-295

Paper / Analysis / dx.doi.org/10.13182/NT70-A28676

Experimental Determination of the Differential Fast-Neutron Flux in the High Flux Isotope Reactor Using Techniques Threshold Detectors

H. L. Dodds, Jr., P. F. Pasqua

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 296-301

Paper / Technique / dx.doi.org/10.13182/NT70-A28677

Reactor Neutron Measurements with Fission Foil-Lexan Detectors

P. F. Rago, N. Goldstein, E. Tochilin

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 302-309

Paper / Technique / dx.doi.org/10.13182/NT70-A28678

The Iodine Collection Efficiency of Activated Charcoal from Hanford Reactor Confinement Systems

J.D. Ludwick

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 310-313

Note / Chemical Processing / dx.doi.org/10.13182/NT70-A28679

Replacement Hafnium Control Rods for the Bonus Reactor

G. M. Tolson, G. R. Davis

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 314-320

Note / Material / dx.doi.org/10.13182/NT70-A28680