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Irradiation Effects in the EGCR Fuel

Description: From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date: June 1965
Creator: Baumann, C. D.
Partner: UNT Libraries Government Documents Department

Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2

Description: The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.
Date: April 7, 1960
Creator: Lees, E. A.; Boyle, R. F. & Spalaris, C. N.
Partner: UNT Libraries Government Documents Department

Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments

Description: From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date: July 1963
Creator: Comprelli, F. A.
Partner: UNT Libraries Government Documents Department

Roll Cladding Uranium-Zirconium and Uranium-Zirconium-Niobium Alloys with Zircaloy-2 for Plate-Type Fuel Elements

Description: From Abstract: "Investigations were made of alternate methods of bonding fuel shapes and the use of alternate core alloys in flat plates. Alternations and additions were made to development facilities needed to fabricate roll-clad plates for the EBWR core. Pilot production of EWBR-type plates proved that the plate cladding process could be adapted to production facilities."
Date: February 1958
Creator: Bean, C. H.; Macherey, R. E. & Lindgren, J. R.
Partner: UNT Libraries Government Documents Department

Ceramic Investigations of UO₂

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department

Temperature distribution in spherical pellets

Description: From abstract: "A study is presented of the surface temperature distribution of spherical pellets in a fixed-bed, pellet-type reactor. The temperature near a point of contact is determined experimentally by means of an electrolytic tank analogue. An analytical approach involving the use of the IBM (CPC) calculator is described. Suggestions for further study are included."
Date: 1953
Creator: Anderson, G. M.
Partner: UNT Libraries Government Documents Department

Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements

Description: From introduction: This report presents the results of the two phases of the work: study of the compatibility of beryllia bodies with a coating material, molybdenum; and studies of beryllia-beryllium body fabrication.
Date: July 31, 1952
Creator: Long, R. E.; Duckworth, W. H.; Saller, Henry A.; Stacy, J. T.; Miller, R. A. & Schofield, H. Z.
Partner: UNT Libraries Government Documents Department

Welding Plutonium-Containing Fuel Elements

Description: Report discussing the manual and automatic welding techniques for fuel elements containing plutonium with Zircaloy-2 aluminum, and stainless steel cladding, 0.013 to 0.0889 cm (0.005 to 0.350 in.) thick" (p. 3).
Date: June 1964
Creator: Lemon, L. C.; Ross, W. T. & Bailey, W. J.
Partner: UNT Libraries Government Documents Department

A Study of the Feasibility of a Tracer System for Locating a Fuel-Element Failure in Reactors

Description: Report discussing a study that investigates the use of small amounts of tracer elements placed in the fuel alloy of subassemblies in order to locate fuel-element failure. Details of experimental methods and materials are included as well as data that leads to the suggestion of further investigation.
Date: November 2, 1956
Creator: Pobereskin, Meyer; Sunderman, Duane Neuman; Eldridge, Aaron; Calkins, George D.; Chubb, Walston; Rough, Frank A. et al.
Partner: UNT Libraries Government Documents Department

The Properties of Uranium Containing Minor Additions of Chromium, Silicon, or Titanium

Description: This report discusses a study regarding the properties of uranium with added chromium, silicon, or titanium. This study was conducted in order to evaluate the effects of alloying on the mechanical properties of base metal.
Date: January 30, 1956
Creator: Saller, Henry A.; Rough, Frank A. & Chubb, Walston
Partner: UNT Libraries Government Documents Department

Development of Cermet Fuel Elements

Description: Abstract: "Fabrication techniques for making metal-ceramic fuel elements containing 60 to 90 volume per cent of UN or UO2 in a Type 302B stainless steel matrix was investigated. A hot press-forging procedure was most successful for fabricating fuel cores with a density of 90 per cent of theoretical or better. This procedure consisted of sealing the cold-pressed core compacts in stainless steel picture-frame packs, heating to 1900 F, and pressing to a total reduction in thickness of 35 per cent. A pressure of approximately 50 tsi ores used. Specimens produced by this method were evaluated on the basis of their microstructure, modules if rupture, electrical conductivity, and resistance to thermal shock. Microscopic and macroscopic examination showed the presence of a continuous metal skeleton even in specimens containing 90 volume per cent fuel. The modulus of rupture at room temperature varied from 22,500 psi for a specimen cnotaining 63 volume per cent UO2. Both the electrical conductivity and resistance to thermal shock of UO2 were improved by the addition of a small volume of metal. Gas-pressure-bonding techniques appear promising for clodding these cores into composite elements."
Date: August 11, 1958
Creator: Paprocki, Stan J.; Keller, Donald L.; Cunningham, G. W. & Kizer, Donald E.
Partner: UNT Libraries Government Documents Department

Centrifugal casting of plate-type fuel elements

Description: From introduction: "Centrifugal casting appeared to be the only method by which the intricate shape could be produced in a cold mold. With this in mind, a program was initiated for the purpose of determining the feasibility of centrifugally casting plates of uranium-5 w.o chromium and uranium-2 w/o zirconium."
Date: November 10, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F. & Murr, William E.
Partner: UNT Libraries Government Documents Department

Low-Melting Alloys for Cast Fuel Elements

Description: The following report follows an investigation made to determine the composition of uranium-rich ternary eutectic alloys most suitable for reactor application in the as-cast condition. These determinations were made based metallographic examination and thermal analysis of as-cast alloys.
Date: May 19, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Partner: UNT Libraries Government Documents Department

Swaged Metal Fiber-UO₂ Fuel Element: Final Report

Description: From introduction: The objectives of this program were to: study the variables of uranium dioxide, metal fibers and cladding material and determine the effects of swaging, develop thermal conductivity tests for small diameter rod-type elements, determine the thermal conductivity of various combinations of metal fibers and uranium dioxide, and select optimum combinations of the above variables to recommend for irradiation testing.
Date: January 1960
Creator: Kane, John
Partner: UNT Libraries Government Documents Department

Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Partner: UNT Libraries Government Documents Department

SRE Fuel Element Damage: An Interim Report

Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
Partner: UNT Libraries Government Documents Department

OMRE Fuel Plate Surface Temperature Measurement

Description: Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
Partner: UNT Libraries Government Documents Department