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Progress Relating to Civilian Applications During April, 1956

Description: A report about elevated-temperature properties of dilute uranium-aluminum and uranium-zirconium alloys. Hot-hardness measurements show that small amounts of wither aluminum or zirconium increase the hardness of uranium at elevated temperatures.
Date: May 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During July, 1956

Description: A report based on a study about the factors which affect the amount of chemical reaction between water and Zircaloy 2 at high temperatures. Also, experimental programs for the measurement of radiation emissivity, chemical reaction rates, and diffusion rates have been completed.
Date: August 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During May, 1956

Description: A report about mechanical properties of dilute uranium alloys are being investigated in an effort to develop a high-strength alloy for fuel elements. Elevated temperature tensile tests were made on two dilute uranium-aluminum alloys, and several ternary alloys were arc melted.
Date: June 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During December, 1956

Description: A report about thermal conductivity measurements which are made on uranium, uranium-1.5 w/o zirconium, and zircaloy 2 for a program that aims to determine the feasibility of using clad specimens. Results from the measurements indicate that the difference in thermal conductivity values between uranium and uranium-1.5 w/o zirconium is less than the anticipated 5 percent.
Date: January 1, 1957
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During February, 1957

Description: A report about the design and construction of equipment for thermal-conductivity measurements of irradiated encapsulated uranium. Metallographic techniques used to confirm solubility limits of uranium in thorium, previously determined by electrical resistivity and X-ray data, have been unsuccessful.
Date: March 1, 1957
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During August 1961

Description: Progress is reported on development studies on reactor materials and components, fuels, fuel elements, gaspressure bonding of ceramic fuel elements, uranium carbides, growth of UO/sub 2/ single crystals, radioisotope and radiation applications, materials evaluations, coated-particle fuel materials, corrosion in fiuoride-volatility processes, cold-bonding processes, radiation effects on MGCR fuel materials, radiation effects on SM-2 fuels, gas-cooled reactor program, and gas-pressure bonding of … more
Date: September 1, 1961
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During February 1959

Description: Measurements of the thermal conductivity of unirradiated U and UO/sub 2/ were completed. An evaluation is being made of the creep properties of annealed and 15% cold-worked Zircaloy-2 at elevated temperatures in order to determine the suitability of Zircaloy-2 for process tubing in the NPR. Single crystals of highpurity Mo are being grown for irradiation studies. Research to identify factors affecting irradiation-induced volume changes sn graphite by means of sink- float density measurements wa… more
Date: March 1, 1959
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During September 1957

Description: Data are given on the creep properties of Zircaloy-2 and Zircaloy-3 at elevated temperatures. Burst strength of welded Zircaloy-2 amd Zr tubes at elevated temperatures is given. A study of the effects of micronizing on UC/sub 2/ is presented. Some uranium corrosion rates in boiling solutions of electrolytes are given. Hardness amd grain-size dnta are given for Nb-alloy strips annealed one hour at 1500 deg C. Experiments are in progress to study the effects of applied bonding load amd the strain… more
Date: October 1, 1957
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During March 1958

Description: The thermal conductivity and electrical resistivity of U encapsulated in Zircaloy-2 with NaK as a heat transfer material were determined prior to irradiation. The short-time rupture strength of 15% cold-worked Zircaloy-2 at 290, 345, and 4OO C is reported. Tests to develop the right-angle method of extrusion cladding of U with Al were continued. Pressure bonding of Al to Niplated U by temperature and gas-pressure tecchniques has produced sound metallurgical bonds. A series of 17 alloy compositi… more
Date: April 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During June 1958

Description: Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs of U, U-l.5 wt. % Zr, and Zircaloy-2 was measured from 20 to 800 C prior to irradiation. Corrosion data for a 1000 hr test at 3O0 C in pure water of nine Zr alloys are given: Zr -Sn-Mo, Zr-Sn-Mo-Nb, Zr - Sn-Mo-Nb (trace Fe and Ni), Zr-Sn-Mo (trace Fe and Ni) Zr-Sn, and Zr-Sn (trace Fe and Ni). Developments for Aluminum-Clad Fanel Elements. Studies continued in casting Al and cladding with Al. Co… more
Date: July 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During July 1958

Description: Data are given on the thermal ccnductivity of Ti--6 wt. % Al--4 wt.% V. The creep strength of 15% cold-worked Zircaloy-2 is being determined for reactor components in the 290 to 400 deg C range. Nine serles of high-strength corrosion- resistant Zr alloys were prepared and corrosion tested. Results are included. The fabrication of Al-U alloys for uses in various reactors is presented. The development of a natural-U fuel alloy with improved corrosion resistance is presented. Results of corrosion … more
Date: August 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During December 1958

Description: Thermal-conductivity measurements were completed from 100 to 600 deg C on UO/sub 2/ specimens. An investigation of the creep properties of annealed and of 15% coldworked Zircaloy-2 in the 290 to 400 deg C temperature range is being conducted. Research to develop a method of sink-float density measurements to identify factors affecting irradiation-induced volume changes in graphite was continued. An increase in the U content of Al-U alloys is desirable as a means of increasing the fuel loading o… more
Date: January 1, 1959
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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