American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 19

Volume 19

Number 1 | Number 2 | Number 3

Number 1

Thermal Analysis of the Pennsylvania State University Breazeale Nuclear Reactor

J. A. Haag, S. H. Levine

Nuclear Technology / Volume 19 / Number 1 / July 1973 / Pages 6-15

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31313

Criticality Safety Evaluation of a Shipping Container for Moderated Low-Enriched Uranium Compounds

Ricardo Artigas

Nuclear Technology / Volume 19 / Number 1 / July 1973 / Pages 16-20

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT73-A31314

Thermal Considerations and Analysis for a Radioactive Waste Repository

R. D. Cheverton, W. D. Turner

Nuclear Technology / Volume 19 / Number 1 / July 1973 / Pages 21-33

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT73-A31315

Compatibility of Refractory Metals with 244Cm2O3

J. R. DiStefano, K. H. Lin

Nuclear Technology / Volume 19 / Number 1 / July 1973 / Pages 34-45

Technical Paper / Material / dx.doi.org/10.13182/NT73-A31316

Monitoring and Measurement of Carbon Activity in Sodium Systems

K. Natesan, T. F. Kassner

Nuclear Technology / Volume 19 / Number 1 / July 1973 / Pages 46-57

Technical Paper / Material / dx.doi.org/10.13182/NT73-A31317

A Dual-Energy Method for Measuring Void Fractions in Flowing Mediums

F. E. LeVert, E. Helminski

Nuclear Technology / Volume 19 / Number 1 / July 1973 / Pages 58-60

Technical Note / Instrument / dx.doi.org/10.13182/NT73-A31318

Number 2

  • Table of Contents
  • Authors(Darrell F. Newman, C. L. Schuske, S. J. Altschuler, M. Martini, A. Gerosa, Paul J. De Meester, A. W. Barsell, R. B. Goranson, P. R. Clements)

Temperature-Dependent k for a ThO2-PuO2 HTGR Lattice

Darrell F. Newman

Nuclear Technology / Volume 19 / Number 2 / August 1973 / Pages 66-83

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31322

Models for the Safe Storage of Dry and Wet Fissile Oxides

C. L. Schuske, S. J. Altschuler

Nuclear Technology / Volume 19 / Number 2 / August 1973 / Pages 84-95

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT73-A31323

Venting Device for Sodium-Cooled Fast Reactor Ceramic Fuel Elements

M. Martini, A. Gerosa

Nuclear Technology / Volume 19 / Number 2 / August 1973 / Pages 96-110

Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31324

A Model for the Embrittlement and Annealing of Irradiated Steel

Paul J. De Meester

Nuclear Technology / Volume 19 / Number 2 / August 1973 / Pages 111-116

Technical Paper / Material / dx.doi.org/10.13182/NT73-A31325

Improved Technology for Multiwatt Radioisotope Heater Units

A. W. Barsell, R. B. Goranson, P. R. Clements

Nuclear Technology / Volume 19 / Number 2 / August 1973 / Pages 117-125

Technical Paper / Aerospace / dx.doi.org/10.13182/NT73-A31326

Number 3

The Effect of Noncondensables on the Rate of Sodium Vapor Condensation from A Single-Rising HCDA Bubble

T. G. Theofanous, H. K. Fauske

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 132-139

Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A15874

Purification of Beryllium by Solvent Extraction from Carbonate Solutions with Quaternary Alkylammonium Carbonate

Forest G. Seeley, David J. Crouse

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 140-147

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT73-A15875

Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels

L. A. James, R. L. Knecht

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 148-155

Technical Paper / Material / dx.doi.org/10.13182/NT73-A15876

Fuel Capsule Vent System Development for the Viking Radioisotope Thermoelectric Generator

Frederick A. Schumann

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 156-164

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT73-A15877

Precession Damping of Solar Probes by Reradiative Forces

Philip T. Choong, Edward A. Mason

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 165-173

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT73-A15878

FFTF Probe-Type Eddy-Current Flowmeter: Wet Versus dry Performance Evaluation in Sodium

T. J. Costello, R. L. Laubham, W. R. Miller, C. R. Smith

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 174-180

Technical Paper / Instruments / dx.doi.org/10.13182/NT73-3

A Photoneutron Antimony-124-Beryllium System for Fissile Materials Assay

H. O. Menlove, R. A. Forster, D. L. Matthews

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 181-187

Technical Paper / Analysis / dx.doi.org/10.13182/NT73-A15880

Track-Etch Radiography: Alpha, Proton, and Neutron

Harold Berger

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 188-198

Technical Paper / Analysis / dx.doi.org/10.13182/NT73-A15881

Assay of Light Water Reactor Rods for Their Uranium-235 Content

K. Böhnel

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 199-201

Technical Paper / Analysis / dx.doi.org/10.13182/NT73-A15882

Neutron Yield from a Small High Purity 238PuO2 Source

J. K. Bair, H. M. Butler

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 202-203

Technical Note / Radioisotope / dx.doi.org/10.13182/NT73-A15883

An In-Reactor Temperature Monitor

G. L. Hofman

Nuclear Technology / Volume 19 / Number 3 / September 1973 / Pages 204-206

Technical Note / Instrument / dx.doi.org/10.13182/NT73-A15884