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INVESTIGATION OF THERMAL-STRESS-FATIGUE BEHAVIOR OF STAINLESS STEELS. Quarterly Technical Progress Report, April-June 1962

Description: Activities in a program to obtain data on thermal-stressfatigue in various stainless steels under reactor conditions are reported. Information concerning procurement of equipment and materials is given along results of initial testing. A specimen of 304 stainless steel was strain-rate tested at 100 to 900 deg C. The averaged result of this test was 0.0005 in./in.-sec. Tensile testing of standard ASTM 1/2-in.-dia stainless steel rods is underway. Data obtained so far in the program are compared … more
Date: October 31, 1963
Creator: Horton, K. E.
Partner: UNT Libraries Government Documents Department
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STRONTIUM-90 FUELED THERMOELECTRIC GENERATOR POWER SOURCE--FIVE-WATT U.S. NAVY WEATHER STATION. Final Report

Description: The SNAP-7C 10-watt Sr/sup 90/ thermoelectric generator, the converter, batteries, and weather station housing that were delivered to Antarctica in December 1961 are described. Thermoelectric analysis, thermal analysis, fuel form and shielding requirements, generator assembly, electrical system, operational tests, and environmental testing are discussed. (M.C.G.)
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
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Radioisotopic heat sources. Revision 1

Description: For the radioisotopes with half-lives over a year, only eight appear to be obtainable in the foreseeable future. The fission products, strontium-90, cesium-137, and promethium-147, exist in wastes from reactor processing, diluted with enormous volumes of other elements and salts. Among those isotopes producible by irradiation of special target materials (cobalt-60, uranium-232, plutonium-238, and curium-244) cobalt-60, though easy to produce, requires a special design for the heat source genera… more
Date: October 15, 1963
Creator: Rohrmann, C.A.
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. June through August1963

Description: This report covers the following titles: (1) The Effects of 8-Methyl Lipoic Acid on the Evolution of Oxygen and Reduction of Carbon Dioxide during Photosynthesis; (2) Further {sup 14}C and {sup 15}N Tracer Studies of Amino Acid Synthesis during Photosynthesis by Chlorella Pyrenoidosa; (3) Two-Dimensional High Voltage, Low-Temperature Paper Electrophoresis of {sup 14}C-Labeled Products of Photosynthesis with {sup 14}CO{sub 2}; (4) A Search for Enzymic and Nonenzymic Reactions Between Thiamine De… more
Date: October 2, 1963
Partner: UNT Libraries Government Documents Department
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A Photographic Study of Boiling Flow

Description: From abstract: A high speed motion picture study was conducted of boiling flow in a vertical, rectangular channel at atmospheric pressure. Three different visual flow regimes were defined and described.
Date: October 25, 1963
Creator: Vohr, John Henry
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, September 1963

Description: This document details activities of the Irradiation Processing Department during the month of August, 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: October 14, 1963
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: September 1963

Description: This report, from the Chemical Processing Department at HAPO for September 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.
Date: October 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Fabrication process test: FPT-63-28, Reduction of in-process inventory

Description: This document details the process of casting plutonium for the purpose of reducing the in-process inventory. The plutonium is cast, then rough machined to produce a storable form, then stored for the ten-day waiting period.
Date: October 30, 1963
Creator: Fisher, J. G.; Lewis, L. I. & Pinkerton, J. M.
Partner: UNT Libraries Government Documents Department
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Fabrication of hot die size diffusion bonded fuel elements for Production Test IP-546-A

Description: Hot die sizing (HDS) is a process being considered at Hanford to replace or supplement the existing AlSi brazing process. Hot die sizing consists of passing a preheated core-component fuel assembly through a cold the to bond the aluminum jacket to the core while passing a die plug through the internal bore to form the internal bond. Fuel end bonding is accomplished in a following step by applying heat and pressure to the sized fuel element. This report summarizes the fabrication of fuel element… more
Date: October 10, 1963
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Nuclear safety criteria for special test loads -- N-Reactor

Description: The initial fuel landing for the N-Reactor and the use of a specific alternative fuel element are described in a previous report. It is highly probable that it will also be desirable in the future to irradiate still other types of fuel elements in the reactor. If the test is of small scale, fever than five channels, or if these elements vary only slightly from the initial fuel load (or any other fuel type approved for large-scale use at some future date), the irradiation will be accomplished wi… more
Date: October 14, 1963
Creator: Nechodom, W. S. & Miller, N. R.
Partner: UNT Libraries Government Documents Department
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U-233

Description: This memorandum discusses the problems associated with the production and use of Uranium 233 for an early test shot.
Date: October 22, 1963
Creator: Smith, A. E.
Partner: UNT Libraries Government Documents Department
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FPT-63-27: Dimensional stability, model 1807 shape castings

Description: Due to sluggish transformation rates of metastable phases, unalloyed Pu continues to shrink after casting. Therefore, a pre-machining holding period is required to promote finished part dimensional stability. This test will determine the holding period commensurate with both this requirement for stability and an optimum material inventory level. Four storage periods will be evaluated (9, 8, 7, 6 days) for dimensional changes and related to parts stored for the standard 10-day period.
Date: October 18, 1963
Creator: Walker, C. M.
Partner: UNT Libraries Government Documents Department
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Interim report I: Production test IP-581-A, half-plant high flocculation pH test at B Reactor

Description: A half-plant high flocculation pH test began at B Reactor on September 24, 1963. The purpose of the test was to determine whether operation of the water plant flocculation basins ad filters at a pH higher than 7.0 with subsequent coolant pH adjustment to 6.6 is beneficial as far as radioactivity in the effluent is concerned. It is planned to increase the flocculation basin pH in steps to a maximum of 7.6. Although primarily an effluent activity test, fuel discharged after a metal cycle at each … more
Date: October 31, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Radiometallury examination of three overbore split failures from 3062C (RM C-422)

Description: Three overbore elements, 75Zl2, 75Zl4, and 75Zl5 were discharged from 3062C on April 16, 1962 with longitudinal splits after an exposure of 676. The three elements, two of which had completely split apart, were received on July 5, 1963 to determine the cause of failure. All three elements had failed in the same manner with several full length longitudinal cracks in the uranium extending radially from the canwall to about midway in the core. The failure mechanism was found to be the same as that… more
Date: October 22, 1963
Creator: Teats, R.
Partner: UNT Libraries Government Documents Department
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Old pile HCR operating temperatures

Description: A study was made to determine operating temperatures of old pile HCR sheaths. The calculations were performed with the aid of a FORTRAN coded program for the IBM 7090. The difficulty of determining the correct value for the contact coefficient between the HCR and the graphite channel at any point in the channel length resulted in performing the calculations in a parametric style. The independent system parameters were varied during the calculations. These parameters are diametral spacing betwee… more
Date: October 10, 1963
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Internal graphite moderator forces study, C and K Reactors

Description: The purpose of this study was to determine the maximum forces that can be imposed by the graphite moderator on prospective VSR channel sleeves. In order to do this, both the origins and modes of transmission of the forces were determined. Forces in the moderator stack that are capable of acting on a block or group of blocks may originate from any of the following primary effects: Contraction of graphite due to irradiation; thermal expansion of graphite; frictional resistance to motion; resistan… more
Date: October 28, 1963
Creator: Cooley, D. E.
Partner: UNT Libraries Government Documents Department
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Increased coolant flow for H reactor

Description: The purpose of this letter is to outline the immediate and long-range plans for increasing the H Reactor coolant flow. The flow can be increased, immediately from the present base of about 84,000 gpm to about 88,000 gpm via the following changes: routine purges; use of non-bumpered fuel; increasing the flow through Fringe enrichment and Fringe Poison tubes by changing orifices; and reaming damaged rear fittings to their original size. The flow can be increased to about 94,000 gpm via the follow… more
Date: October 23, 1963
Creator: Huffman, I. L.
Partner: UNT Libraries Government Documents Department
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Exceeding always-safe ratio in F-2 and F-1 tanks: Number 2, CY-63

Description: The always critically-safe ratio of plutonium to enriched uranium was exceeded in the F-2 and V-1 vessels on June 6, 1963. The allowable always-safe ratio at the time of the incident vas 627 grams per ton. The actual ratio achieved vas 673 grams per ton. This report details the investigation into events leading to the over-batch.
Date: October 7, 1963
Creator: Malody, C. W.
Partner: UNT Libraries Government Documents Department
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Interim report V, production test IP-549-A half-plant low alum feed water treatment at F Reactor

Description: A half-plant low alum water treatment test began at F Reactor on January 16, 1963. The test, which had been prompted by the analysis of ledge corrosion attack on fuel elements, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from the normal production fuel irradiated in process water treated with two different alu… more
Date: October 18, 1963
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Production of special nuclear materials in N-Reactor

Description: In the summer of 1962, a brief scoping study of the N-Reactor`s capability as a producer of tritium concurrently with plutonium and steam was completed and documented. This study indicated that there might be considerable incentive in pursuing the development of a multi-product mode of operation of the N-Reactor. Early in 1963 reports presented the preliminary production and cost data, and brief discussions of the potential technical problems which mav arise in a multi-product mode of operation… more
Date: October 21, 1963
Creator: Condotta, D. L. & Pierick, E. G.
Partner: UNT Libraries Government Documents Department
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Reactor physics monthly technical progress report, September 1963

Description: The activities included the single tube fuel element study, production losses encountered upon simultaneous irradiation of Np{sup 237}target material, startup measurements of lattice parameters and spectral indices, neutron lifetime in N-Reactor, production estimates for tritium only, FLEX code, etc.
Date: October 1, 1963
Creator: Nichols, P. F.
Partner: UNT Libraries Government Documents Department
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