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Volume 19

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