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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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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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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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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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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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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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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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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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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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Centrifugal Casting for Plutonium and Plutonium-Uranium Plates

Description: The objective of this investigation was to determine the feasibility of centrifugal casting to produce fuel element plates suitable for use in a power reactor. Preliminary investigations involving the centrifugal casting of metal plates suitable for use in a power reactor proved to be successful. Lead plates cast at medium speeds contained very few voids and exhibited a surface which conformed very closely to that of the mold.
Date: November 28, 1956
Creator: Quinlan, F. B. & Tverberg, J. C.
Partner: UNT Libraries Government Documents Department
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Corrosion of Stainless Steel, Titanium, and Tantalum in Plutonium - Nitric Acid Solutions

Description: The letter E. R. Irish/W. H. Swift to R.E. Burns and H. H. Hopkins, dated August 15, 1956, subject Plutonium Concentration Problems, requested information on corrosion of stainless steel, titanium, and tantalum in plutonium nitrate-nitric acid solution, with and without sulfate ion. Experimental conditions and results of tests designed to yield the requested information are given below.
Date: November 27, 1956
Creator: Brunstad, A.
Partner: UNT Libraries Government Documents Department
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An Ultrasonic Method for Bond Testing Reactor Fuel Elements

Description: Ultrasonic testing has been investigated as a possible non-destructive method for checking the bond integrity of certain type fuel elements. Equipment has been developed to inspect experimental fuel elements for various research programs. Circuits have been devised to discriminate the size of defects and to map the areas which are unbonded.
Date: November 27, 1956
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
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Evaluation of Peerless Magnetic Drive Process Pump

Description: The desirability of employing leakproof process pumps for handling the corrosive and radioactive process solutions in the H.A.P.O. separations plants has led to the establishment of a program for the development and testing of packless pumps with particular emphasis on evaluation of commercially available units. One such pump, its operating characteristics and behavior, are described in this report.
Date: November 19, 1956
Creator: Dunn, J.
Partner: UNT Libraries Government Documents Department
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Post-Irradiation Examination of Cluster-Type Fuel Elements

Description: Cluster fuel elements meet many of the requirements of high temperature recirculating water reactors and have several advantages over solid fuel elements. Operation at higher specific power levels for a given temperature limit are attainable because of the larger heat transfer surface. Failure of a single rod in cluster does not restrict coolant flow as severely as failure of a solid fuel element, hence the number and severity of stuck charges can be reduced.
Date: November 19, 1956
Creator: Boyd, C. L.
Partner: UNT Libraries Government Documents Department
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Note on Power Recovery From Warm Water

Description: Several studies of power recovery from Hanford pile effluents have been made, from which the conclusion can be drawn that, while recovery of power is feasible, it is costly because of the large volume of vapor which must be handled per kilowatt-hour of energy provided. This note is to call attention to the possibility of developing cheaper machinery than the conventional low-pressure turbine stages considered in previous studies through use of a water expansion cycle.
Date: November 15, 1956
Creator: Wood, E. C.
Partner: UNT Libraries Government Documents Department
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PRPR Control Requirements. Part I.

Description: The following remarks are intended primarily to assist in the orientation of the PRP reactor control development program in a direction consistent with the basic objectives of the program as a whole, and to discuss certain aspects of particular control systems which have a bearing on the capabilities of the reactor with respect to these objectives.
Date: November 14, 1956
Creator: Triplett, J. R.
Partner: UNT Libraries Government Documents Department
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Radiobiological Studies of the Columbia River Through December, 1955

Description: Radiobiological studies were made to determine effects of radioactive effluents from the Hanford reactors upon the aquatic biota of the Columbia River and to evaluate related hazards. Data from studies completed between September, 1945, and December, 1955 are presented and interpreted. All forms of life were many times more radioactive than the water they inhabited. Some radioisotopes were much more readily accumulated than others in living organisms. Differences in the concentration of certain… more
Date: November 7, 1956
Creator: Davis, J. J.; Watson, D. G. & Palmiter, C.C.
Partner: UNT Libraries Government Documents Department
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Trip Report Consultation on Organic Reactor Coolants

Description: There is a continuing high interest in the development of organic coolant technology for application to future Hanford reactors. In addition to the HAPO organic program, two other programs are being sponsored by the Atomic Energy Commission. These include the Naval Reactor program, aimed at a reactor for ship propulsion, and the Civilian Power Reactor program. Because of the similarity of the technical efforts in the three programs, an attempt is being made to establish effective liaison among … more
Date: November 5, 1956
Creator: Atwood, J. M.; Cook, M. W. & Eddy, P. P
Partner: UNT Libraries Government Documents Department
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Stability of Chromel-Alumel Thermocouples in Carbon Dioxide at 1000°C

Description: Tests on twenty identically prepared 26 gauge Chromel-Alumel thermocouples have been completed. It appears that wires of this material without protection are unsatisfactory mechanically and thermoelectrically for service in atmospheres of CO₂ at 1000°C.
Date: November 29, 1955
Creator: Burton, H. H.
Partner: UNT Libraries Government Documents Department
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Purification of Mercury Metal

Description: Mercury to be used in polarography as a dropping mercury electrode must be of the highest purity. The author has found that much of the commercial "triple-distilled" mercury as well as that which is repurified on site is not sufficiently pure and because of this, a study of mercury purification techniques was made and a very satisfactory procedure was tested thoroughly. This procedure is described in detail in this report.
Date: November 22, 1955
Creator: Koyama, Karl
Partner: UNT Libraries Government Documents Department
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A Review of the MPC's for Natural Thorium

Description: The possible hazards from the refining and processing of thorium are of wide interest in atomic energy work. A review of the data available was made at Hanford in the last year to support consultations on the hazards of radioisotopes with other plants which may handle thorium. Since a major discrepancy between the published values of air MPC's and the metabolic data was noted, a review of the calculations on thorium was made in order to obtain the best estimates available. This document tabulat… more
Date: November 21, 1955
Creator: Healy, J. W.
Partner: UNT Libraries Government Documents Department
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A Kinetic Study of the Fluoride Catalyzed Nitric Acid Dissolution of Thorium Metal

Description: The penetration rates of thorium metal by boiling nitric acid were measured as a function of the concentration of fluoride catalyst and of nitric acid. Dissolved thorium and aluminum were found to inhibit the reaction. Thoris exhibited penetration rates much lower than those of thorium metal. In addition to the specific rate measurements, pot type batch dissolvings were carried out to estimate plant time cycles. An empirical mathematical equation was devised which correlates the results of thes… more
Date: November 17, 1955
Creator: Goodall, C. A.; Hepworth, J. L.; Moore, R. L. & Watts, Jr., R. A.
Partner: UNT Libraries Government Documents Department
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