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EURATOM PROGRAM "Improved Zirconium Alloys"

Description: Introduction: "This report is an expanded version of the regular monthly letter report and is prepared in this form with the intention of reviewing work on the subject program for Euratom technical personnel. Work performed during the month of September, which normally constitutes the entire letter report, has been condensed under one heading."
Date: October 5, 1960
Creator: Weinstein, Daniel & Van Thyne, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Boron-Carbon System: Quarterly Report Number 1, May - June 1960

Description: Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. Alloys are being produced by sintering pressed powder aggregates with subsequent arc melting. Alloys have been made at two atomic percent intervals up to thirty atomic per cent carbon. In the future, higher carbon compositions are to be investigated. Techniques have been worked out for the metallographic preparation of the extremely h… more
Date: August 5, 1960
Creator: Elliott, Rodney P. & Van Thyne, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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KAPL-120-8A Test Assembly Thermocouple Failure.

Description: This document reports the circumstances surrounding the failure of sheathed thermocouples during a test being conducted in the KAPL-120 Loop. The report is prepared to provide a record of these events and to acquaint those who use these thermocouples for testing of other applications with the difficulties that are sometimes encountered.
Date: February 5, 1960
Creator: Dearing, F. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Fretting Corrosion of ZR-2

Description: Although the corrosion of resistance of Zircaloy--2 clad fuel elements in high temperature water is excellent, some concern has been expressed in regard to the resistance against fretting corrosion. Since this form of corrosion can proceed quite rapidly it could induce fuel element failure through penetration of the cladding. Fretting corrosion if it occurred, would take place either where the fuel element contacted the process tube or where portions of the fuel element contacted each other, e.… more
Date: February 5, 1960
Creator: Lobsinger, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Aluminum for use in Reactors Cooled by High-Temperature Recirculating Water

Description: aluminum has been considered as a material for cladding fuel elements to be used in reactors cooled by high-temperature recirculating water. Aluminum is abundant, chap, has a relatively low cross section for thermal neutrons, and is readily fabricated into complex shapes. For these reasons, it appears that the use of aluminum rather than steel, Zircaloy or other candidate materials for fuel element cladding, would result in considerable savings in operating expense. The actual economics will of… more
Date: April 5, 1960
Creator: Ayres, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials

Description: This is the third of a series of reports describing the phases of a study of the wear and galling of autoclavedZircaloy-2 by various bearing surface materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 surfaces will not prevent scratching. It also showed that metals softer than Zircaloy-2 in general do not scratch it. The second report (2) described how eight metals and alloys were wear-tested on autoclaved Zircaloy-2 as prospects for fuel elemen… more
Date: July 5, 1960
Creator: Weber, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials

Description: Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date: December 5, 1960
Creator: Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Transport Calculation of the HFIR Beam Hole Currents

Description: An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tan… more
Date: December 5, 1960
Creator: Claiborne, H. C. & Rakavy, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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