The Post-Irradiation Examination of a PuO₂-UO₂ Fast Reactor Fuel (open access)

The Post-Irradiation Examination of a PuO₂-UO₂ Fast Reactor Fuel

From abstract: "Post-irradiation examination consisted of dimensional measurements, gamma scans, determination of fission gas release, visual examination of the fuel, measurement central voids, and metallographic examination of selected samples.
Date: November 1961
Creator: Gerhart, J. M.
System: The UNT Digital Library
Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR (open access)

Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR

From abstract: "The design, fabrication, and irradiation results are described for a 0.028 inch thick 304 stainless clad fuel element (SH-4B) exposed in the Vallecitos Boiling Water Reactor loop under superheat conditions."
Date: September 1, 1961
Creator: Spalaris, C. N.; Boyle, R. F.; Evans, T. F. & Esch, E. L.
System: The UNT Digital Library
Fabrication of Fuel Rods by Tandem Rolling (open access)

Fabrication of Fuel Rods by Tandem Rolling

From introduction: "The purpose of this report is to present the details of the exploratory and developmental work on tandem rolling, and the subsequent fabrication of tandem rolled fuel rods for irradiation testing in the Vallecitos Boiling Water Reactor."
Date: July 1961
Creator: Lingafelter, J. W.
System: The UNT Digital Library
Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI (open access)

Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI

From introduction: "Once-Through boiling of water to 100 per cent steam quality was successfully accomplished. Results of Departure from Nucleate Boiling, transition, and film boiling tests are presented."
Date: May 1, 1961
Creator: Polomik, E. E.; Levy, S. & Sawochka, S. G.
System: The UNT Digital Library
Steam-Cooled Power Reactor Evaluation: Study of 300 Mw(e) Once-Through Superheater Reactor (open access)

Steam-Cooled Power Reactor Evaluation: Study of 300 Mw(e) Once-Through Superheater Reactor

From introduction: "This report presents a conceptual design study of the once-through superheat reactor design based on experimental heat transfer results obtained during the fall of 1960 on Task F-2 of the AEC sponsored Nuclear Superheat Project."
Date: January 1961
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library