15 Matching Results

Search Results

Results: 1 - 15
open access

Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: July 1963

Description: This is the thirty-fifth progress report from July 1963 detailing progress made in areas such as the process of completing the final helium tests and examining the specimens generated under Tests 1 and 2, the shakedown stage of Test 3, and Test 4 being in progress.
Date: August 15, 1963
Creator: Andrews, R. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department
open access

FCX element load test

Description: No Description Available.
Date: August 15, 1963
Creator: Zibritosky, G. & Lancaster, R.
Partner: UNT Libraries Government Documents Department
open access

Grain Growth of UO$sub 2$. Part I

Description: No Description Available.
Date: August 15, 1963
Creator: Hausner, H.
Partner: UNT Libraries Government Documents Department
open access

Grain Growth of UO2. Part I

Description: Abstract: (1) Grain growth in UO2 pellets was studies between 100 C and 2600 C. The pellets were encapsulated in small vacuum-tight tungsten containers in an argon atmosphere. (2) The grain size-time relationship could be expressed by an equation. A low exponent, m>_ 1/3, was found in those experiments and is related to the type of UO2 investigated. An activation energy of 65 kcal/mole was obtained for the grain growth process. The time exponent, m, increased with increasing temperature if the … more
Date: August 15, 1963
Creator: Hausner, H.
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories monthly activities report, July 1963

Description: This is the monthly report for the Hanford Laboratories Operation, July 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: August 15, 1963
Partner: UNT Libraries Government Documents Department
open access

Hazards Summary Report for the Metal Assembly

Description: Information required to obtain authorization to receive and use a fast critical assembly for operation with the General Atomic linear accelerator is documented. The analysis offers evidence showing that operation of the assembly will create no undue risk to the health and safety of the public or the personnel of the Laboratory. Experiments with the accelerator pulsed fast assembly will consist primarily of measurements of neutron yield and pulse shape produced by the electron pulses from the Li… more
Date: August 15, 1963
Creator: Brown, J. R. & Russell, J. L.
Partner: UNT Libraries Government Documents Department
open access

Hydraulic Characteristics of HNPF 8-Rod Fuel Element

Description: Pressure drop and vibration characteristics were determined for an 8-rod fuel element model of the design intended for use with uranium carbide (UC) in the Hallam Nuclear Power Facility (HNPF). Measurements with water as the test fluid were converted to equivalent values for sodium, the HNPF coolant, using the principles of dimensional similitude. Initially UC elements will be concluded in an HNPF core loading comprised primarily of 19-rod U-Mo fuel elements. In this core loading, the UC fuel e… more
Date: August 15, 1963
Creator: Begley, R. J.
Partner: UNT Libraries Government Documents Department
open access

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Partner: UNT Libraries Government Documents Department
open access

Mixtures of Metals With Molten Salts

Description: A review is presented of various types of solutions of metals in molten salts, especially in their own molten halides. With relatively little reference to the older literature, the progress made in the last 20 years is discussed. Roughly, the solutions are classified into two groups: The metal may retain, to some degree, its metallic properties in the solution, or it may lose them through strong interaction with the salt solvent. The alkali-metal systems are typical examples of the former type,… more
Date: August 15, 1963
Creator: Bredig, M. A.
Partner: UNT Libraries Government Documents Department
open access

NUCLEAR FUEL (OXIDE) CLAD THERMIONIC CONVERTERS. Quarterly Technical Progress Report, May 1 through July 31, 1963

Description: Fabrication of the components for the FDM-1 converter and its back-up device was completed. The FDM-1 converter was assembled, and preparations for testing were completed. Performance testing was initiated, and a total of 330 hours of operation above 1000 deg K in a cesium environment were logged. The peak emitter temperature reached was 2000 deg K with a thermionic output of nearly 2 watts/cm/sup 2/. Indications of a cesium leak were observed, and the device was shut down for examination. A 50… more
Date: August 15, 1963
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Quarterly Project Report: Sixteenth Quarter, May-July 1963

Description: From introduction: "This is the sixteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: August 15, 1963
Creator: Flock, W. L.
Partner: UNT Libraries Government Documents Department
open access

Pathfinder Atomic Power Plant. Design and Operation of a Boiling and Superheating Heat Transfer Loop

Description: A test loop was designed and fabricated for the study of the heat transfer and fluid flow characteristics of boiler and superheater fuel elements at heat fluxes of 70,000 to 500,000 Btu/hr-ft/sup 2/. The design and operation of the loop are described. D-c resistance heating at low voltages was used. Control, instrumentation, and shakedown tests are discussed. Runs performed to date are described. (D.L.C.)
Date: August 15, 1963
Creator: Jerman, R. B. & Healy, M.
Partner: UNT Libraries Government Documents Department
open access

REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, JULY 1963

Description: Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III, ZPR-VI, ZPR-VII, Faret, EBR-I, EBR-II, Borax-V, Treat, Fermi Fast Breeder Reactor, magnetohydrodynamic cells, thermionic cells, rocket fuel test reactor, and HiC critical assembly. Reactor technology is reported on fuel development and properties, heat engineering, physics, materials development, chemical separations, nuclear safety, and nondestructive testing. (N.W.R.)
Date: August 15, 1963
Partner: UNT Libraries Government Documents Department
Back to Top of Screen