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Temperature distributions in a reactor fuel plate (open access)

Temperature distributions in a reactor fuel plate

A report pertaining to heat-transfer characteristics , the supercritical water reactor, and flat fuel plates separated by cylindrical spacers perpendicular to the plates.
Date: 1954
Creator: Long, J. K.; Chastain, Joel W.; Redmond, R. F.; Jung, R. G. & Fawcett, Sherwood L.
System: The UNT Digital Library
Temperature distributions in a reactor fuel plate (open access)

Temperature distributions in a reactor fuel plate

Report detailing local heat-transfer coefficients as they relate to temperature distribution in reactor fuel plates.
Date: 1953
Creator: Chastain, Joel W.; Long, J. K.; Redmond, R. F.; Grimble, R. E. & Dayton, R. W.
System: The UNT Digital Library
The tensile strength of solid-state bonded aluminum and nickel-plated uranium (open access)

The tensile strength of solid-state bonded aluminum and nickel-plated uranium

A report intended to aid in the evaluation of solid-state bonding techniques for cladding natural-uranium fuel-element cores with aluminum, tensile specimens which are 1/4 in. in diameter and 3 in. long.
Date: 1954
Creator: Saller, Henry A.; Dickerson, R. F. & Carlson, R. J.
System: The UNT Digital Library
Ternaries of the eutectic uranium-chromium alloy (open access)

Ternaries of the eutectic uranium-chromium alloy

A report about a study about the effect of small additions of iron, nickel, and manganese to the uranium - 5 wt % chromium eutectic alloy.
Date: 1953
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, A. A.
System: The UNT Digital Library
Theoretical Studies of the Solidification of Uranium Castings (open access)

Theoretical Studies of the Solidification of Uranium Castings

Report discussing a method of evaluating factors relevant to the creation of sound uranium castings. From abstract: "A mathematical model has been developed to calculate the time-temperature relationships in a cylindrical uranium casting during its solidification. Finite-difference equations are used, and the solution is obtained by use of a digital computer."
Date: July 11, 1958
Creator: Fletcher, Billie L.; Foster, Ellis L., Jr.; Franklin, Charles K.; Lechler, Andrew; Schwartz, Benjamin L. & Dickerson, Ronald F.
System: The UNT Digital Library
The thermal and electrical conductivities of zirconium and its alloys (open access)

The thermal and electrical conductivities of zirconium and its alloys

A report which intends to present an empirical formula, based on available experimental data, to correlate the thermal and electrical conductiviities of sirconium and sirconium alloys.
Date: 1951
Creator: Bing, George; Fink, F. W. & Thompson, H. B.
System: The UNT Digital Library
Thermal cycling of specimens of uranium-chromium alloys (open access)

Thermal cycling of specimens of uranium-chromium alloys

A report about the effects of thermal cycling upon specimens of the uranium-chromium eutectic alloy.
Date: 1955
Creator: Saller, Henry A.; Dickerson, Ronald F. & Murr, William E.
System: The UNT Digital Library
Thermodynamic evaluation of materials in contact with fluoride fuels (open access)

Thermodynamic evaluation of materials in contact with fluoride fuels

A report about the corrosion tendencies of 64 metallic elements, nonmetallic elements, and carbides evaluated by means of thermodynamic methods.
Date: 1954
Creator: Crooks, R. C.; Sparrow, D. E.; Ward, J. J. & Filbert, Robert B., Jr.
System: The UNT Digital Library
Topical report on anion-exchange studies on the separation and purification of uranium and thorium (open access)

Topical report on anion-exchange studies on the separation and purification of uranium and thorium

A report which describes the separation of uranium from thorium in carbonate, hydrochloric acid, and sulfuric acid solutions by anion-exchange resins.
Date: 1950
Creator: Poirier, R. H. & Bearse, A. E.
System: The UNT Digital Library
Topical Report on Chemical Process to Recover Uranium from Phosphate Rock (open access)

Topical Report on Chemical Process to Recover Uranium from Phosphate Rock

The following report summarizes research done on dissolving uranium from phosphate rock and superphosphate and recovering it from solution in a more concentrated form.
Date: November 15, 1947
Creator: Igelsrud, Iver
System: The UNT Digital Library
Topical report on examination of residues from the nitric acid digestion of pitchblende (open access)

Topical report on examination of residues from the nitric acid digestion of pitchblende

A report about an investigation started to determine the compounds and/or minerals present in the residue resulting from nitric acid digestion of ore. Emphasis was placed on determining the compounds and/or minerals containing boron.
Date: 1950
Creator: Langston, B.; Tangel, O. F. & Richardson, A. C.
System: The UNT Digital Library
Topical Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Topical Report on Refining of MgX and Other Uranium-Bearing Materials

This report discusses a study which explores the effects of feed and acidity on extractive methods. From abstract: "Results from fractional precipitation of MgX from dilute sulfuric acid solutions indicate that, in the presence of sufficienct iron, phosphate is precipitated as ferric phosphate, and not as uranyl phosphate."
Date: December 31, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
Topical report on spectrophotometric determination of small amounts of uranium in phosphate rock, shales and similar materials (open access)

Topical report on spectrophotometric determination of small amounts of uranium in phosphate rock, shales and similar materials

A report which provides procedures for sample decomposition and the determination of small amounts of uranium in the phosphate rocks and shales. Also, the cupferron and ether-extraction methods are discussed.
Date: 1947
Creator: Center, E. J.
System: The UNT Digital Library
A Tracer Study of the Transport of Chromium in Fluoride Fuel Systems (open access)

A Tracer Study of the Transport of Chromium in Fluoride Fuel Systems

The following report follows an experimental study that was made on the mass transport of chromium in polythermal inconel-fluoride fuel systems, followed by the technique of adding radioactive chromium-51 to the system as either CrF3 in the salt or as elemental chromium in the solid phase.
Date: June 18, 1957
Creator: Price, Robert B.; Sunderman, Duane Neuman; Pobereskin, Meyer & Calkins, George D.
System: The UNT Digital Library
Tungsten-Arc Welding of Ames Thorium and Thorium Alloys (open access)

Tungsten-Arc Welding of Ames Thorium and Thorium Alloys

This report follows an investigation made on the welding of Ames thorium by the inert-gas-shielded tungsten-arc process as the first part of a program on the joining of thorium. This program is part of a broader research program to develop the technology of thorium.
Date: January 15, 1952
Creator: Monroe, Robert E.; Martin, D. C. & Voldrich, C. B.
System: The UNT Digital Library
Uranium Migration in UOâ‚‚-Bearing Ceramics (open access)

Uranium Migration in UOâ‚‚-Bearing Ceramics

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
System: The UNT Digital Library
Uranium recovery from a low-grade Katanga sulfide concentrate : topical report (open access)

Uranium recovery from a low-grade Katanga sulfide concentrate : topical report

A report which describes a variety of methods for processing a low-grade sulfide concentrate from the Congo. This concentrate consists primarily of sulfides of cobalt, nickel, and iron, plus about 10 percent uranium, present principally as uraninite.
Date: 1953
Creator: Bearse, A. E.; Ewing, R. A.; Sclar, C. B. & Pobereskin, M.
System: The UNT Digital Library
Use of electrical measurements to detect differences among uranium tetrafluoride samples : final report (open access)

Use of electrical measurements to detect differences among uranium tetrafluoride samples : final report

A report which contains a summary of the research during the period September 1, 1951, to January 31, 1952, on the utilization of electrical measurements to detect chemical and physical differences in various samples of UF4.
Date: 1952
Creator: Reynolds, D. C. & Middleton, A. E.
System: The UNT Digital Library
Vapor-Deposited Zirconium on Uranium (open access)

Vapor-Deposited Zirconium on Uranium

From introduction: "This report describes the second phase of the work on the application of protective coatings to uranium by vapor deposition to reduce or prevent its corrosion by water."
Date: July 20, 1955
Creator: Powell, Carroll F.; Jones, Robert P.; Girod, Fleet T. & Campbell, Ivor E.
System: The UNT Digital Library
Welded Closures for Fuel Elements (open access)

Welded Closures for Fuel Elements

From abstract: "The inert-gas metal-arc welding process was used to determine weldability studies of various aluminum alloys that are being considered for use as can materials. The solid-phase and induction welding processes were also investigated for making can closures."
Date: October 8, 1953
Creator: Sopher, R. P.; Martin, G. E.; Grable, G. B.; Voldrich, C. B.; Leatherman, A. F. & Todd, F. C.
System: The UNT Digital Library
Welding of High-Strength Stainless Steels for Pressure Vessels (open access)

Welding of High-Strength Stainless Steels for Pressure Vessels

The following report describes the welding characteristics of several high-strength stainless steels that were considered for use as a pressure vessel to operate at high pressures at 800 F.
Date: April 5, 1954
Creator: Vagi, J. J.; Thompson, V. R. & Martin, D. C.
System: The UNT Digital Library
Zirconium Pilot Plant Research and Development Progress Report (open access)

Zirconium Pilot Plant Research and Development Progress Report

The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.
Date: September 20, 1951
Creator: Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System: The UNT Digital Library
Zirconium Pilot Plant Research and Development Progress Report (open access)

Zirconium Pilot Plant Research and Development Progress Report

The following report studies the effect of flow rates and deposition pressure on the zirconium deposition in the zirconium pilot plant with the use of a Hilco oil purifier for the vacuum pumps that permitted studies to continue through the month.
Date: November 20, 1951
Creator: Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System: The UNT Digital Library
Zirconium Research and Development : Progress Report (open access)

Zirconium Research and Development : Progress Report

From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."
Date: October 15, 1950
Creator: Bulkowski, H. H.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
System: The UNT Digital Library