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Volume 1

Number 5

Ordered Packed-Bed Fuel Elements

H. Susskind, W. E. Winsche, W. Becker

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 405-411

Technical Paper / dx.doi.org/10.13182/NT65-A20549

Stainless-Steel-Clad Fuel Rod Failures

R. N. Duncan, W. H. Arlt, H. E. Williamson, C. J. Baroch, J. P. Hoffmann, T. J. Pashos

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 413-418

Technical Paper / dx.doi.org/10.13182/NT65-A20551

Evaluation of Highly Irradiated Yankee Fuel Cladding

W. R. Smalley

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 419-424

Technical Paper / dx.doi.org/10.13182/NT65-A20552

Performance of Thin-Walled Stainless-Steel-Clad Fuel Rods

D. R. McClintock, E. Paxson, H. M. Ferrari

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 425-431

Technical Paper / dx.doi.org/10.13182/NT65-A20553

Boron Stainless-Steel Fuel-Element Cladding in the Indian Point Reactor

C. R. Johnson

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 432-438

Technical Paper / dx.doi.org/10.13182/NT65-A20554

Fatigue and Burst Tests on Irradiated In-Pile Stainless-Steel Pressure Tubes

L. A. Waldman, M. Doumas

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 439-445

Technical Paper / dx.doi.org/10.13182/NT65-A20555

Corrosion Product Behavior in Stainless-Steel-Clad Water Reactor Systems

G. Russell Taylor, Paul Cohen

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 446-452

Technical Paper / dx.doi.org/10.13182/NT65-A20556

Development of Test to Simulate Intergranular Cracking of Nonsensitized Stainless Steel in Water Reactor Environments

A. E. Pickett, W. L. Pearl, M. C. Rowland

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 453-461

Technical Paper / dx.doi.org/10.13182/NT65-A20557

Radiation Effects on the Mechanical Properties and Microstructure of Type-304 Stainless Steel

J. S. Armijo, J. R. Low, U. E. Wolff

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 462-477

Technical Paper / dx.doi.org/10.13182/NT65-A20558

Influence of Preirradiation Heat Treatment on the Postirradiation Ductility of Stainless Steel

W. R. Martin, J. R. Weir

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 478-483

Technical Paper / dx.doi.org/10.13182/NT65-A20559

Inhibition of Chloride Stress Corrosion Cracking of Austenitic Stainless Steel

C. R. Bergen

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 484-489

Technical Paper / dx.doi.org/10.13182/NT65-A20560

Formation of Cyanide in Liquid Sodium

E. W. Hobart, R. G. Bjork

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 490-492

Technical Paper / Technical Note / dx.doi.org/10.13182/NT65-A20561