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Thermal Contact Conductance of Fuel Element nateriasls

Description: Thermal Resistance of the contact between to core and the jackets or unbonded fuel elements may easily be the largest source of error in core temperature predictions. The object of this work is to improve contact conductance predictions by measuring conductance of the joint between reactor fuel and cladding materials at joint pressures, temperatures and thermal flux levels approaching reactor service conditions.
Date: April 10, 1959
Creator: Wheeler, Robert G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and Preliminary Testing of Powder-Lock Feeder

Description: At the request of 234-5 Development, studies of a system for controlling plutonium powder transfer were undertaken by Process Equipment Development. This report presents details of equipment designed to fulfill requirements and proposes equipment for installation on additional Hot Button Line prototypes.
Date: April 3, 1959
Creator: Dunn, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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1706 KE Water Treatment for Out-of-Reactor Test Facilities.

Description: Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date: March 30, 1959
Creator: Demmitt, Thomas F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Protection of Stainless Steel Sheathed Thermocouples from Uranium at 500 C

Description: Ceramic insulated, stainless steel sheathed thermocouples have been used to monitor temperatures of encapsulated uranium specimens, both in-reactor and out-of-reactor. No operational difficulties are encountered at low temperatures, but at a temperature of 700 C or greater, a eutectic is formed between uranium and iron. This reaction destroys protective sheath and results in thermocouple failure. A typical example of the phenomenon has been reported by J.W. Geffard of the Fuels Development Oper… more
Date: March 30, 1959
Creator: Sake, J.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRTR Fuel Element Nuclear Safety

Description: A study of the nuclear safety in the storage and transportation of PRTR fuel elements has been made. This study was based on 7-rod clusters of plutonium-aluminum allow fuel elements containing 1.8 per cent Pu by weight. Each cluster is 7 feet 4 inches in length and contains 270 grams plutonium. Drawings of the "New Fuel Storage Pit" (H-3-11030) have been reviewed for nuclear safety. Nuclear safety criteria for the design of a lead shielded fuel transfer cask as well as criteria for the storage … more
Date: March 30, 1959
Creator: Ketzlach, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Polishing and Etching of Uranium Dioxide

Description: Various methods and procedures for preparing uranium dioxide bodies for metallographic examination and study have been utilized by various investigators. Unfortunately, these methods are not in general satisfactory for use on irradiated uranium dioxide. Since radiation damage studies on irradiated uranium dioxide require use of electron microscopy, and reveal structure by virtue of surface relief. This report covers an investigation of etching methods compatible with radiometallurgy and electro… more
Date: March 23, 1959
Creator: Thomas, K. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Induction Melting of Uranium Dioxide Powder

Description: Fused uranium dioxide has desirable characteristics for fabricating high density nuclear fuel elements by swaging. Methods of preparing dense uranium dioxide particles being investigated at HAPO include are arc fusion, and sintering and crushing of low density powder. This paper reports the results of exploratory experiments to prepare fused uranium dioxide by induction heating of low density powder in graphite crucibles.
Date: March 21, 1959
Creator: Newkirk, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Proposed Mechanism for the Corrosion of Aluminum in Water

Description: Data has been previously presented to show that aluminum corrosion in high temperature water may proceed with either a parabolic or a linear dependence on time. The rate of the parabolic process is an Arrhenius function of temperature and essentially independent of alloy composition. More recently several aluminum melts have been tested which corrode by a logarithmic rate process.
Date: March 19, 1959
Creator: Millon, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of In-Reactor test Loops on PRTR Operation and Program

Description: Recently proposals for justifiable additions to the Plutonium Recycle Test Reactor Complex were presented to the Atomic Energy Commission at their request. In addition to a critical reactivity measuring facility in the fuel element storage basin, the following in-reactor loops were proposed: 1. A high pressure, H2O cooled fuel test loop. 2. A rupture loop to investigate fuel element failures. 3. One or more materials testing loops.
Date: March 18, 1959
Creator: Peterson, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report - February 1959

Description: Plutonium Oxide Fuels. Mixtures of PWR grade UO2 containing 10, 20, 30, 40, 50, and 60 w/o PuO2 were sintered in hydrogen for 44 hours at 1600 C to get additional data on solubility in this system. Densities of all the pieces were low, approximately 80 percent of theoretical; however, solid solution formation was complete in every case. The low density material should not affect lattice parameter values, but it did slightly reduce the intensity of the reflections.
Date: March 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Scintillation Nuclear Incident Alarm Monitor

Description: This report was written to describe the instrument and test results obtained. It is understandably imperative that such alarming devices be incorporated in various areas of the plant to provide an alarm or warning for increasing dose rate from gauss radiation fields.
Date: March 13, 1959
Creator: Spear, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Photographic Observations of the Growth of Uranium Dioxide Crystals by Vapor Deposition

Description: Photographic observations of the behavior of uranium dioxide at high temperatures are of great value in designing and evaluating fuel elements. This paper reports the growth of uranium dioxide crystals by vapor deposition during out-of-reactor and in-reactor experiments.
Date: March 9, 1959
Creator: Bates, J. L. & Newkirk, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Simulation of an Electromagnetic Nondestructive Test on an Analog Computer

Description: The purpose of this report is to show the impedance of an approximate equivalent circuit on a complex plan for various constant frequencies and different metals. The equivalent circuit represents a testing coil driven with an AC voltage and a network to represent the impedance of the metal.
Date: March 9, 1959
Creator: Cameron, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Moderator Height on Reactor and Vertical Flux Distribution in PRTR

Description: Primary control of the PRTR is achieved by regulating the level of the heavy water moderator which is held in the reactor vessel by a helium gas balance system. Emergency shutdown is effected by a gas-balanced moderator dump system which drain the moderator from the calandria at a rapid rate. This report presents a quantitative appraisal of the reactivity effects due to moderator level changes in controlling or scramming the reactor. In conjunction with the reactivity calculations, solutions we… more
Date: March 3, 1959
Creator: Reginmbal, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Piping Components for Organic Coolant Systems

Description: Organic compounds have been considered for use as reactor coolants for two primary reasons. First, the high boiling points of the compounds would permit the reactor to operate at high temperature without the need for the high pressure required when water is used as a coolant. Secondly, the compounds are less corrosive than water and would permit the use of carbon steel rather than stainless steel components in the reactor. Unfortunately, the organic compounds proposed for use as reactor coolant… more
Date: March 3, 1959
Creator: Floyd, H. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Process Vessel Precision and Accuracy Estimates

Description: The following is an attempt to explain the method by which the precision associated with an observed volume reading in a process vessel (E-12, C-1) should be calculated based upon a regression analysis of cumulative data. There are two types of volume measurement consists of estimating the total volume in a vessel at some inventory time. A transfer measurement consists of estimating the volume between two levels within a tank.
Date: March 2, 1959
Creator: Hough, C. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Reactivity of Uranium Monocarbide and Uranium Mononitride with Water at 100°C.

Description: The monocarbide and the mononitride of uranium are potentially useful ceramic nuclear fuel materials. This paper reports the results of exploratory investigations of the reactions of uranium monocarbide and uranium mononitride with boiling water. Uranium dioxide, chemically stable in deoxygenated boiling water, was used as a control.
Date: February 26, 1959
Creator: Newkirk, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scratch Depth Measurement Methods

Description: Judging scratch depth or surface roughness by unaided visual inspection under controlled conditions, while rapid and popular, is not quantitative. Comparison methods improve reproducibility but are generally not applicable to evaluation of depths of single widely spaced scratches. Stylus-type contour recorders yield valuable scratch contour data but may themselves plow through soft materials and fine details. Depth measuring microscopes are particularly applicable to measurement of pinhole dept… more
Date: February 26, 1959
Creator: Brenden, B.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Detailed Procedure for K Reactors Rear ace Decontamination by Chemical Flush or the Rear Crossheaders, Pigtails and Nozzles as Authorized by the Production Test Authorization IP-239-N.

Description: The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected tha… more
Date: February 25, 1959
Creator: Crossman, W.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Random Loading of E-Metal Dissolver

Description: Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid … more
Date: February 25, 1959
Creator: Ketzlach, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report- July, August, September 1958 Plutonium Fuels Development Plutonium Metallurgy Operation

Description: Examination of Al- 1.65w/o Pu and Al- 12 w/o Si- 1.65 w/o Pu capsules irradiated 55- 60% burnout of the plutonium atoms revealed a 1.4% volume increase and no apparent microstructural changes. A four rod cluster containing Al-8 w/o Pu and Al-12 w/o Si-8 w/o Pu alloy cores is currently under irradiation in Loop 3 of KE Reactor at a water temperature of approximately 230C. A second cluster has been fabricated an is scheduled for charging late in 1958. Two seven-rod clusters for irradiation in KE… more
Date: February 24, 1959
Creator: Wick, O.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Nuclear Safety of Fissile Materials

Description: Whenever fissile materials are handled in significant quantities such as in fuel element fabrication, separation processes, or in exponential and/or critical experiments a potential criticality hazard exists. The usual procedure which is followed by those persons conducting critical mass experiments is to either place the potential reactor in a heavily shielded cell or to conduct the experiments remotely in which case distance provides a measure of safety in the event of an unscheduled radiatio… more
Date: 1959-02-11?
Creator: Clayton, E.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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