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Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis

Description: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly apparent in the analysis of syste… more
Date: November 30, 1959
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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Decontamination of the KER Rupture Experiment Loop. Test Series B - Tests No. 3. Test Series D-Test No. 1.

Description: The first series of tests in the KER-REP-1 loop proved that a fission product contaminated loop could be decontaminated to a safe level for contact maintenance. Since a good decontamination process was available, there was much that could be improved about this process. Further testing of this process and several variations of other processes have been scheduled. The evaluation of these processes includes specific decontamination factors, process corrosion, and loop activity reduction factors (… more
Date: November 25, 1959
Creator: Weed, R. D.
Partner: UNT Libraries Government Documents Department
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Shielding Efficiency of Heavy Element Neoprene Gloves at Low X-Ray Energies

Description: The utilization of gloves wherein heavy element additives have been included is a significant means of reducing exposure to hands and, consequently, increasing allowable working time in operations which require direct contact with low energy isotopes - such as plutonium. The number of such gloves available has been limited considerably by the feasibility of fabrication and the practicality of application. The following study was made on two basic gloves - the first, a heavy zinc-neoprene coated… more
Date: November 23, 1959
Creator: Mehas, T. C.
Partner: UNT Libraries Government Documents Department
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Technical Investigation of Autoclave Failure

Description: On July 31, 1959, an autoclave ruptured while being used for thermal cycling studies of Plutonium Recycle Test Reactor (PRTR) plutonium-aluminum fuel elements. Since stand-in materials were being used in this test, no contamination was involved. This accident could lead to inference of greater hazards associated with PRTR fuel designs than had previously been postulated. An ad hoc technical investigation committee was appointed by the Manager Reactor and Fuels Research and Development, to stud… more
Date: November 18, 1959
Creator: Wittenbrock, N. G.; Freshley, M. D.; Griggs, B. & Wheeler, R. G.
Partner: UNT Libraries Government Documents Department
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Continuous Ion Exchange Development - A Qualitative Review

Description: Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facili… more
Date: November 10, 1959
Creator: Nicholson, G. A.
Partner: UNT Libraries Government Documents Department
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Decontamination of the KER Rupture Experiment Loop Test Series B - Tests No. 1 and 2

Description: The first series tests in the KER-REP-1 loop proved that a fisssion product contaminated loop could be decontaminated to a safe level for contact maintenance. The second series of tests ere scheduled for a more thorough evaluation of these processes includes specific decontamination factors, process corrosion rates, loop activity reduction factors (loop decontamination factors), and any preferential decontamination which may be present.
Date: November 2, 1959
Creator: Weed, R. D.
Partner: UNT Libraries Government Documents Department
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High-Speed Saw Tests Power Reactor Fuels Reprocessing Development

Description: The basic scheme for processing power reactor fuels at Hanford includes the removal of inert endfittings ("hardware") from the active sections of the fuels. Within Hanford Laboratories, research and development studies have been in progress on various types of saws which might be used for hardware cutoff. In the initial phase of the program, high-speed saws were investigated; more recently, studies on low speed saws have been conducted. This report summarizes the high speed saw studies and incl… more
Date: November 18, 1959
Creator: Kelly, V. P.
Partner: UNT Libraries Government Documents Department
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Magnetic-Force Resistance Butt Wielding of Zircaloy-2 Fuel Element Closures

Description: Zircaloy-2 has a strong tendency to absorb oxygen and nitrogen at elevated temperatures. These gas impurities are extremely harmful, causing brittleness and loss of corrosion resistance. The production of ductile corrosion-resistant welds by present methods required shielding of the weld metal by an inert gas atmosphere or by a vacuum. The alternative to an inert gas atmosphere or a vacuum is reduction of the welding time to a few milliseconds of time to prevent gas absorption.
Date: November 16, 1959
Creator: Mills, L. E.
Partner: UNT Libraries Government Documents Department
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A Simple Telephone Telemeter

Description: When following the performance of automatic and semi-automatic equipment that is left unattended for extended periods of time, it is often desirable to be able to check this equipment by remote means. A convenient vehicle for such a check is the telephone since nearly all locations have or can have a telephone extension installed. The check of the equipment may be made as simple or extensive as desired, with the outcome of the check represented by a relay condition, for example. The condition o… more
Date: November 2, 1959
Creator: Ratcliffe, C. A.
Partner: UNT Libraries Government Documents Department
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Specification for Requisition G-3855923Xircalogy-4 Jacket Tubing

Description: This specification is specifically designed for the procurement of Zircaloy tubing to be used in the of swaged, UO fuel elements, an, and the Pu fuel elements for the Plutonium Recycle Test Reactor. Requisition G-385923 contains the following information pertinent to this specification: 1. Dimensions and dimensional tolerance. 2. Source of zirconium sponge and conditions for us of Zircaloy scrap. 3. Inspection requirements. 4. Shipping instructions.
Date: November 6, 1959
Creator: Oakes, H. P.
Partner: UNT Libraries Government Documents Department
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Confinement System Instrumentation

Description: Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date: November 6, 1959
Creator: Richards, W. A.
Partner: UNT Libraries Government Documents Department
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The Anodizing of Zirconium

Description: Five continuous coatings were produced on zirconium coupons using an anodizing technique. These layers appear to be quite adherent and not subject to visible or audible failure caused by flaxion of the basis metal, Their abrasion resistance, though not investigated thoroughly, appears to be moderately good.
Date: November 3, 1953
Creator: Ray, William E.
Partner: UNT Libraries Government Documents Department
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Some Comments on the Selection of Operating Temperatures for DPR

Description: The results of this investigation indicate that maximum electric power generation can be obtained by selecting the turbine steam temperature within a range of plus/minus 30 degrees C. from an "idealized" steam temperature. This "idealized" steam temperature is shown to depend primarily on the maximum permissible uranium temperature. The minimum available condenser temperature and the temperature rise of the coolant in the pile effect the selection of the turbine steam temperature to lesser ex… more
Date: November 16, 1953
Creator: Altmann, Manfred.
Partner: UNT Libraries Government Documents Department
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Final Report: Production Test No 105-505-SI. Exposure of Two Different Types of Rubber to Pile Water

Description: In connection with different seals for C & D equipment it appears advantageous that many parts could be made of rubber or other elastic polymers. However, data on the deterioration rate of these materials under irradiation are somewhat scant in the available literature. It appears that for neutrons and pure gamma radiation that a good grade of natural rubber stands up best in all the test reported and because the results of the neutron irradiation are so closely correlated with results from g… more
Date: November 18, 1953
Creator: Cooke, J. P.
Partner: UNT Libraries Government Documents Department
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Coulometric Determination of Phosphate

Description: The conventional volumetric micro-determination of phosphate depends upon the precipitation of phosphomolybdate, filtration and washing of the precipitate, and titration with standard base. The method is slow and tedious, subject to many interferences, and is not applicable to samples containing less than 1-2 mg of phosphate. Other weak acid anions, such as carbonate or acetate, interfere in the method. Strong acid anions, such as nitrate, sulfate, and chloride do not interfere.
Date: November 19, 1953
Creator: Carson, W. N., Jr. & Gile, H. S.
Partner: UNT Libraries Government Documents Department
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The Hydrogen Content of Fabricated Uranium

Description: The hydrogen contents of several types of fabricated uranium have been determined by a vacuum method and expressed in terms of ccH2/ccU. The data indicate that alpha-rolled metal contains about 0.25 ccH2(STP)/ccU whereas beta heat-treated uranium yielded values between 0.30 and 0.37 cc per cc. Restricted efforts were made to determine where in the heat treatment the 5 to 10 cc of hydrogen per slug were taken up. It appears that no one operation is wholly responsible for this additional gas, … more
Date: November 30, 1953
Creator: Ray, W. E. & Bowen, H. C.
Partner: UNT Libraries Government Documents Department
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A Comparative Study of Hanford and Utah Range Sheep

Description: Observations on sheep representing flocks in Utah adjacent to the Nevada Proving Ground were compared with findings made on experimental sheep exposed to various amounts of radioiodine. The Utah sheep showed no evidence of the radiation damage observed in experimentally treated sheep. Estimations of amounts of radioiodine on vegetation required to cause serious thyroid damage following a contamination event are included.
Date: November 30, 1953
Creator: Bustad, Leo K.; Marks, S.; Dockum, N. L.; Kalkwarf, D. R. & Korrberg, H. A.
Partner: UNT Libraries Government Documents Department
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The Accumulation of Radioactivity as Shown by a Limnological Study of the Columbia River in the Vicinity of Hanford Works : Preliminary Report

Description: The following report provides data collected during an investigation in the Columbia River. The purpose of this investigation was to research the radioactivity present in the bottom-living organisms of the river.
Date: November 12, 1948
Creator: Coopey, R. W.
Partner: UNT Libraries Government Documents Department
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Biology Seminar : methods of assaying for plutonium in biological materials

Description: From introduction: "Since plutonium is manufactured at the Hanford Works, a study of its effect on biological materials is important. To determine the amount of plutonium deposited in a biological sample, it is necessary to have an accurate method for extracting plutonium from these samples. Some of the different methods for plutonium assay are reviewed and given in this paper."
Date: November 1948
Creator: Case, A. C.
Partner: UNT Libraries Government Documents Department
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Effect of Temperature on Beta-Ray Measurements

Description: Summary: "This report investigates photographic methods of measuring beta radiation and includes a study of temperature effects on these measurements. Experimental data are submitted to show that an increase in film temperature before and during beta irradiation causes a definite increase in density for the same dosage. Recommendations drawn from experience gained in the experimental works are offered."
Date: November 23, 1949
Creator: Stevens, A. J.
Partner: UNT Libraries Government Documents Department
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Density and Viscosity of Solutions in the Tributyl Phosphate Process for Uranium Recovery

Description: The following report discusses the presentation of preliminary density and viscosity data which may explain whether higher viscosities of the Deo Base-TBP systems, and a change in density differences between the two phases will lead to unsatisfactory column operation.
Date: November 29, 1949
Creator: Burger, L. L. & Slansky, C. M.
Partner: UNT Libraries Government Documents Department
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