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Welded Seal-Ring Vacuum Closures

Description: This is a preliminary report dealing with the development of bakeable high-vacuum flanges for the ORNL PIG Facility. A number of flange designs are discussed together with fabrication, inspection, testing, and installation and maintenance information.
Date: August 21, 1959
Creator: Michelson, C.
Partner: UNT Libraries Government Documents Department
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The Armour Dust Fueled Reactor (ADFR). Final Report Covering the Period February 21, 1958 to February 21, 1959

Description: Dust circulation studies were conducted in a 2-in.diam. glass tubing loop, 5 x 5 ft, at gas velocities of 100 and 150 fps. Most of the studies were done with Al/sub 2/O/sub 3/ in air, but some were done with U0/sub 2/2 in N/sub 2/ . Two-group criticality calculations for a graphite-reflected and moderated U/ sup 235/ burner gave approximate values of core size and fuel concentration. Investigation of axial variations in fuel density indicate that the axial neutron flux and power distributions d… more
Date: October 21, 1959
Creator: Krucoff, D; Langford, D.; Loewe, W. E.; Narin, F. & Rymarz, T. M.
Partner: UNT Libraries Government Documents Department
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Determination of the Zr Corner of the Zr-Fe-Sn System at 0.1 and 0.2% Oxygen Levels. Final Report for December 5, 1957 - December 5, 1958

Description: This program was undertaken to supply fundamental information on the effect of adding 0.1 or 0.2% oxygen on the phase relationships in the Zr-Fe-Sn system in a limited range of dilute alloys. It is of both theoretical and practical interest to learn that oxygen stabilizes not only the g-phase in zirconium but also two intermetallic compounds ZrFe2 and the G-phase, which, chemically, appears to be Zr4Sn with about 8% Fe replacing zirconium, is shown to be stable at 1010 C, and probably also at 1… more
Date: January 21, 1959
Creator: Lillie, C. Robert
Partner: UNT Libraries Government Documents Department
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Investigation of Mechanical Methods of Scale Removal from HRT Heat Exchangers

Description: Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4in. O.D. x 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employe… more
Date: July 21, 1959
Creator: Gabbard, C. H.; Eissenberg, D. M.; Moyers, J. C. & Namba, I. K.
Partner: UNT Libraries Government Documents Department
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Multigroup Diffusion Theory Calculations for Recent Critical Experiments

Description: In connection with the program of the measurement of eta for U233, several critical experiments have been performed by R. Gwin and D. W. Magnuson of ORML with light water solutions of uranyl nitrate (highly enriched in either U233 or U35) in an essentially bare sphere 27 inches in diameter. This report presents the results of two multigroup-diffusion-theory calculations for the above experiments performed by C. B. Mills and associated at Los Alamos. Assumer cross sections, material concentratio… more
Date: July 21, 1959
Creator: Nestor, C. W., Jr
Partner: UNT Libraries Government Documents Department
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Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A

Description: Property changes to common graphites resulting from reactor irradiation depends strongly on the temperature of exposure. Radiation affects at 30 C and 400 to 500 C are quite well known; however, at intermediate temperatures, results are not well known although a large volume of graphite in most reactors operate in this range. Production test, IP-22A, was reactivated, after a dormant period of many months, to study radiation damage between 30 and 400 C. This report concerns mainly the experiment… more
Date: October 21, 1959
Creator: Koyame, K.
Partner: UNT Libraries Government Documents Department
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Transient Pressures Developed by Sodium-Nitric Acid Reactions

Description: The Atomic Energy Commission has assigned Hanford Atomic Products Operation the responsibility of reprocessing some of the slightly enriched uranium fuel elements from nuclear power reactors. Some stainless steel clad fuel elements contain sodium or a sodium-potassium alloy as a heat transfer medium between metallic core and outer sheath. The nature of the reaction between water and sodium is well known; however, the reaction between sodium and an oxidizing acid is more energetic and not so wel… more
Date: October 21, 1959
Creator: Huck, C. E. & Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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Stack Effluent Monitor Operation and Maintenance

Description: The Stack Effluent Radioisotope Monitor is an instrument which continuously measures and records the amounts of each of several different radioactive isotopes in the stack effluent of the Redox Facility. An informal report, HW-56151, describing the theory of operation and the circuits was prepared and is available to Hanford personnel from the technical files. The formal report, HW-56151 Rev, containing essentially the same information, is available from the Office of Technical Services, Depar… more
Date: July 21, 1959
Creator: Harvey, R. A.
Partner: UNT Libraries Government Documents Department
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A Remote Phase Separation Bulb for Highly Radioactive Sample Analyses

Description: Extraction systems involving chelating agents are widely used in radiochemical separations on a control basis due to the economy in time and equipment. In the case of waste streams, the element of interest is, by definition, at a very low concentration in the presence of gross fission product activities. The resultant large sample size necessary for a reliable analytical results creates a marked radiation hazard to laboratory personnel.
Date: July 21, 1959
Creator: Campbell, M. H.
Partner: UNT Libraries Government Documents Department
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An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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Uranium Cold Extrusion

Description: Several hollow uranium cores of "C" size I & E diameters were fabricated by cold extrusion (550 to 750 F) at Hunter Douglas Aluminum Corporation. Results show diameter control and reproducibility are excellent. Preferred orientation induced by this process is completely removed by a single standard beta heat treatment.
Date: April 21, 1959
Creator: Riedeman, G. W.
Partner: UNT Libraries Government Documents Department
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Remote Area Scintillation Monitoring System

Description: This report was written to describe briefly several possible variations of such systems along with probable cost estimates. Previous work has been shown that the application of scintillation detectors is the simplest and most reliable means for such monitoring. By proper detector selection and measuring methods, the system can be of an approximate gamma dose-rate with gamma energy independence above about 100 Kev. The same system using detector change only is directly applicable to beta, gamma,… more
Date: April 21, 1959
Creator: Spear, W. G.
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.
Partner: UNT Libraries Government Documents Department
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Comparative Costs Of Sea Disposal And Land Burial For The Radioactive Wastes Of The Lawrence Radiation Laboratory

Description: This report is a comparative cost study of radioactive waste disposal for the Lawrence Radiation Laboratory (UCRL). In particular, it compares the costs of sea disposal in depths of 1000 fathoms and of 2000 fathoms off the California coast with land burial of the wastes at the Hanford Atomic Products Operation (HAPO), Richland, Washington, at the National Reactor Testing Station (NRTS), Idaho Falls, Idaho, or at the Nevada Test Site (NTS), Nevada. In the comparison, the cost of utilizing a comm… more
Date: January 21, 1959
Creator: Nielsen, Elmer
Partner: UNT Libraries Government Documents Department
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Braze Alloys v.s. Atmospheres : Final Report Project 1325

Description: Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, suffici… more
Date: May 21, 1959
Creator: Rogers, S. L.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, April 1959

Description: Production of Pu from separations plants was only 58% of April commitment because of Purex difficulties. UO{sub 3} production, shipments met schedules. Pu shape production and shipments exceeded forecast by 14%. Purex HS column, repaired Oct 1958, developed another leak and was bypassed April 18, resulting in Pu and U that required reprocessing. A Palm recovery run at Purex with all- reducing flowsheet, resulted in 87% recovery and excellent decontamination of product. The prototype dual-pass s… more
Date: May 21, 1959
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Record Report: April 1959

Description: This document details activities of the irradiation processing department during the month of April, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and engineering operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.
Date: May 21, 1959
Partner: UNT Libraries Government Documents Department
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Air-Core Strong Focusing Synchrotron

Description: This report addresses air-core strong focusing synchrotron.
Date: April 21, 1959
Creator: Christofilos, N. C.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, May 1959

Description: Pu production from separation plants during May was 116% commitments. UO{sub 3} production and shipments met schedules. Button output and shape production was 97 and 121% of schedule/forecast. Recuplex (product recovery) operated at record rates. Processing at Purex was carried out with the HS column bypassed. Palm processing resulted in excellent product quality but with low yield. A sample of fission products was prepared for Curtiss-Wright. Piping modifications were made to the Purex Pu ion … more
Date: June 21, 1959
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly record report, March 1959

Description: This document details activities of the irradiation processing department during the month of March, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: April 21, 1959
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, November 1959

Description: The November 1959 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)
Date: December 21, 1959
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, December 1958

Description: This document details activities of the irradiation processing department during the month of December 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering operation; Employee Relations Operation; and Financial Operation.
Date: January 21, 1959
Partner: UNT Libraries Government Documents Department
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Production test IP-285-C measurement of operating temperatures of uncooled thermal shield cooling tube

Description: The purpose of this test is to obtain data that may be used as a basis for revising certain Process Standards applying to the cooling or existing reactor shields. The data may also be useful in connection with NPR thermal shield design work. The fact that one of the H reactor bottom thermal shield cooling tubes presently has a flow blockage makes possible an immediate opportunity for test data without undue risk other than that already encountered. Procedures, costs, and hazards of the test are… more
Date: September 21, 1959
Creator: Smalley, W. L.
Partner: UNT Libraries Government Documents Department
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