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Progress Relating to Civilian Applications During April 1958

Description: Results are given from studies on: mechanical properties of Zircaloy-2; preparation of Al--U alloys; effects of N, Ca, Zr, and Mo on electrical properties of UO/sub 2/; effect of chloride, fluoride, and sulfate contamination on corrosion of type 304ELC stainless steel in boiling HNO/sub 3/; density of Mallinckrodt slag and MgF/sub 2/-base materials; development of gamma-phase U alloys; preparation of U--Nb alloys; oxidation of Nb and Nb alloys in dry air at 1000 and 1200 deg C; thermal expansio… more
Date: May 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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Progress Relating to Civilian Applications During April 1959

Description: 5 8 5 of 15% cold-worked Zircaloy-2 as material for process tubes for the NPR has indicated the need for study of the creep properties at elevated temperatures. Single crystals of high-purity Mo are being tify factors affecting irradiation-induced volume changes in graphite by means of sink-float density measurements was continued. The simulation of conditions after lossof- coolant incident in the PRTR by means of a digital computer was continued. The study of the radiometric analysis of Mg was… more
Date: May 1, 1959
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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Progress Relating to Civilian Applications During August 1958

Description: Measurements of thermal conductivity and electrical resistivity were continued on irradiated specimens of UO/sub 2/-clad in Zircaloy-2 with NaK as the heat-transfer medium. The creep strength of 0.15% cold-worked Zircaloy-2 is being determined at elevated temperatures. Work continued on the development of highstrength corrosion-resistant Zr alloys. Research to develop a method of sink- float density measarements to identify factors affecting irradiation-induced volume changes in graphite was co… more
Date: September 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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Progress Relating to Civilian Applications During August 1959

Description: Data are presented on the creep properties of 15% coldworked Zircaloy-2 at 290, 345, and 400 deg C. The progress on the development of an isotopic- exchange fuel-element leak-detection system is summarized. A program to develop a thermal-neutron-flux monitoring system for Hanford reactors is reported. Work on the radiometric analysis of calcium in cement was continued. A surveillance program is in progress to determine the effects of fastneutron irradiation on the mechanical properties of AISI … more
Date: September 1, 1959
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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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
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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
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Progress Relating to Civilian Applications During December 1956

Description: Research is reported in the development of materials for Hanford reactors, development of Al-clad fuel elements, plant assistance to MCW, reactions between water and Zr alloys, general fuel element development, Zr - U alloy studies, corrosion of Zr, reactor materials development, physical metallurgy, development of PWR, and NaTa compatibility at high temperatures. (For preceding period see BMI-1136.) (T.R.H.)
Date: January 1, 1957
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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Progress Relating to Civilian Applications During December 1957

Description: Creep properties of 15% cold-worked Zircaloy-2 at elevated temperatures sre presented. Work has continued on extrusion claddings flat plates utilizing the right-angle tooling. Study of uranium oxide structures has continued with emphasis being placed on determinng residule contents in UO/sub 2/. Four melting experiments were made using pure uranium dingot stock to meassure the total quantity of gas evolution occuring at various controlled temperature levels in the 2000 to presented in the Zr-1 … more
Date: January 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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
open access

Progress Relating to Civilian Applications During December 1959

Description: >The creep and stress-rupture propenties of annealed and of 15% cold- worked Zircaloy-2 are being determined at of a AgBr fuel-element leak detector for use in watercooled reactors. The development of a thermal-neutronflux monitoring system was directed toward extending the sensing-probe life, increasing the effective instrument range, and improving the instrument reliability. Resistivity of Al/sub 2/O/sub 3/-MoSi/sub 2/-UO/sub 2/ ceramic tubes was determined to investigate the effects of MoSi/… more
Date: January 1, 1960
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
open access

Progress Relating to Civilian Applications During December 1960

Description: Research areas include: reactor materials and components; alloy fuels; fission-gas release from refractory fuels; fuel-element development; gas-pressure bonding of ceramic, cermet, and dispersion fuel elements; development of uranium carbide; physical research; radioisotope and radiation applications; void- distribution and heattransfer studies; development of uranium mononitride; materials development and evaluation; coated-particle fuel materials; problems associated with recovery of spent fu… more
Date: January 1, 1961
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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
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Progress Relating to Civilian Applications During February 1958

Description: The creep properties of 16% cold-worked Zircaloy-2 are being evaluated over the 232 to 299 deg C temperature range. helium density measurements were made on samples of UO/sub 2/, and the results are tabulated. Phase boundaries in the Zr--1 wt.% U alloy system were studied. Results of 168-hr corrosion testing of U--Nb and U--Mo alloys in 680 deg F water are given. The reaction between U and water or water vapor is being studied at temperatures ranging up to 200 deg C. Data are given on the hardn… more
Date: March 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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
open access

Progress Relating to Civilian Applications During February 1960

Description: Preliminary results from electrical studies indicate that the "valence- compensated", air-fired U/sub 3/O/sub 8/-La/sub 2/O/sub 3/ solid solutions containing greater than equimolar amounts of La/sub 2/O/sub 3/ are poor conductors. Progress is reported on work devoted to fabrication and evaluation of U/sub 3/O/sub 8/ solid solutions contairing 40. 50 and 60 mole% La/sub 2/O/ sub 3/. and a sample containing 25 mole% Y/sub 2/O/sub 3/ and MgO each. In an investigation on the effects of combined ult… more
Date: March 1, 1960
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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Progress Relating to Civilian Applications During February 1961

Description: Reactor Materials and Components. The stresses required to produce creep rates of 0.001, 0.01, and O.l%/hr at 650, 800, and 1000 deg C were measured for Nb--2.37 wt.% Cr, Nb--3.34 wt.% Zr, snd Nb--5.21 wt.% V; anneals of these three alloys showed recrystallization only for heat treatment at 1260 deg C. Fabrication of miniature heating elements and thermocouples for a power-balancing thermal neutron fiux sensor is described. Fuels. Rolling propenties of Nb-10 wt.% U and Nb--20 wt.% U at 1000 deg… more
Date: March 1, 1961
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
open access

Progress Relating to Civilian Applications During January 1958

Description: Data are given on: creep propenties of 15% coldworked Zircaloy-2; the liquidus in Al-U; effect of chloride on corrosion of type 304 ELC stainless steel; corrosion testing of stainless steels, Ti 75A lead, and rigid PVC as container materials for HNO/sub 3/-recovery process; viscosities of MgF/sub 2/ and MgF/sub 2/-MgO slags; phase boundaries in the U-Zr-H system; oxidation of Nb, Nb-W, and Nb-V alloys in dry air at 1000 and 1200 deg C; nonoxidizing properties of UO/sub 2/- La/sub 2/O/sub 3/ and… more
Date: February 1, 1958
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
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