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Completion Report An Automatic Fuel Element Stamping Machine

Description: This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
Partner: UNT Libraries Government Documents Department
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Classification of PuO2 Particles

Description: The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.
Date: January 6, 1960
Creator: Burnham, J. B.
Partner: UNT Libraries Government Documents Department
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Study Report: High Speed Data Acquisition System for PRTR

Description: High speed data handling and computing systems are coming into increasing use in the automatic control of complex industrial processes. One of the next significant developments in reactor design is believed to be the application of high speed data handling and control systems to nuclear reactors. This document is a study of such a system intended for use with the Plutonium Recycle Test Reactor.
Date: January 20, 1960
Creator: Clark, R. G.
Partner: UNT Libraries Government Documents Department
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Oxygen Removal with Hydrazine- Interim Report

Description: During normal operation the NPR will function as a closed system and the coolant will be maintained at a high degree of purity. Periodically, however, the system will have to be opened for fuel element discharge and/or decontamination. During these periods the reactor will be operated on single pass cooling. The use of deionized and deoxygenated water as the single pass coolant is not economically feasible due to the large quantities of coolant that will be required. At present it appears that… more
Date: January 25, 1960
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
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Summary Report - Pump and Agitator Development 1959

Description: A part of the development activities of the Process Equipment Development Group, Chemical Development, HLO through the year 1959 has consisted of test evaluation of some of the never products of manufacturers, design and refinement of novel units to do certain specialized jobs and development of improved components for existing plant equipment. Modification of present chemical processing methods and investigation of new basic procedures have made it necessary to utilize different and "exotic" m… more
Date: January 13, 1960
Creator: Dunn, J.
Partner: UNT Libraries Government Documents Department
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Final Report of Piping Components for Organic Coolants

Description: Organic compounds with high boiling points and low corrosion qualities have been considered for use as reactor coolants and moderators. Those being considered, however, have a greater tendency to leak than does water. A program to evaluate mechanical closures to be used for a leak-tight system for organic fluids has been established. Report HW-59446 covered descriptions of the facility used in this study and the primary results of tests covering two liquids, fittings, and instrumentation. This … more
Date: January 12, 1960
Creator: Floyd, H. L.
Partner: UNT Libraries Government Documents Department
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Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles

Description: In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations woul… more
Date: January 25, 1960
Creator: Gartin, W. J.
Partner: UNT Libraries Government Documents Department
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Ultrasonic Resin Level Detector

Description: This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
Partner: UNT Libraries Government Documents Department
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Final Report A CG-791 Containment Test

Description: This report describes and evaluates the Hanford 105 reactor building structures' ability to withstand an internal pressure increase. The means by which their roof and wall surface would contain a pressure buildup 0.3 psi, and prevent contaminant release which might accompany a nuclear incident are discussed. Prototypes of the B, D, DR, F, and H reactor block wall configuration, the corrugated transite roof of the K reactors, and the corrugated transite walls of the K and C reactors are evaluate… more
Date: January 1, 1960
Creator: Jensen, H. F.
Partner: UNT Libraries Government Documents Department
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NPR Single Pass Decontamination

Description: The design of NPR shows large quantities of carbon steel pipe and fittings in the front and rear face areas. These are also the area where the most work must be done during an outage, and consequently lower radiation levels are needed here than elsewhere in the piping system. A single pass decontamination of the front and rear piping without going through the entire loop is desirable. Because of the quantities of chemicals and available down time, an effective shorty interval process is needed.… more
Date: January 20, 1960
Creator: Neibaur, G. E.
Partner: UNT Libraries Government Documents Department
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Decontamination of the Irradiated Rupture Prototype with Peroxide-Carbonate and Apace

Description: Considerable work has been done on decontamination procedures for both corrosion products and fission products. Testing of promising procedures under typical rupture conditions is an important phase of this work. The Irradiated Rupture Prototype (IRP) has been used since August in this evaluation work. This document is one of a series reporting these data.
Date: January 13, 1960
Creator: Neibaur, G. E. & Weed, R. D.
Partner: UNT Libraries Government Documents Department
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EGCR Lattice Radial and Angular Power Distribution

Description: One of the problems encountered in the design of the EGCR has been the possibility of bowing in the outer six rods of the seven rod cluster. The power distribution in an outer rod is asymmetrical with respect to the center of the rod. This causes a variation in the cladding temperature, and might result in unven thermal expansion, or bowing.
Date: January 19, 1960
Creator: Nichols, P. F.
Partner: UNT Libraries Government Documents Department
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Once Through Decontamination Studies- Interim Report No. 1.

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has also been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This report contains information on a series of tests performed in the 242-B single pass flow facility. Information concerning the following are presented: (1) Efficiency of decontaminating KER Loop 1 and 2 contaminated specimens. (2) Efficiency of… more
Date: January 12, 1960
Creator: Perrigo, L. D. & Hekenson, J. F.
Partner: UNT Libraries Government Documents Department
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Effect of the PRTR Fuel Elemental Rupture Test Facility on Plutonium Recycle Program Objectives.

Description: To insure a full evaluation of the effects of in-reactor loops with respect to all phases of the Plutonium Recycle Program, a separate study of each loop has been undertaken. An initial study was carried out which analyzed the effects of in-reactor loops using the design criteria for the gas loop as a basis. As soon as the design criteria for the H2O high pressure loop became available, a more detailed evaluation was completed for that loop. Recent completion of the scope description of the PRT… more
Date: January 29, 1960
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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An Initial Study of the Wear and Galling of Various Fuel Element Support Materials of Autoclaved Zircaloy-2

Description: An ex-reactor test stimulating the charging of a tubular fuel element in a Zircaloy-2 process tube showed a problem of severe process tube scratching and galling may occur if metal sliding contact fuel element supports are used. Both the fuel supports and the process tubes were autoclaved. Although the conditions of this test were severe in that the sharp edges rather than a flat surface of the supports were in contact with the process tube, it pointed out the potential problem of galling by po… more
Date: January 14, 1960
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Pyrophoricity of Uranium in Reactor Environments

Description: Report discussing information relative to the pyrophoricity of uranium for the purpose of reactor core fire safety. The report includes physical and chemical properties of uranium.
Date: January 22, 1960
Creator: Zima, G. E.
Partner: UNT Libraries Government Documents Department
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