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Modified-Graphite Technology : Quarterly Report No. 1

Description: From abstract: "This report summarizes the past year of study of fine, molded, multicrystalline graphites with particular reference to the interrelation among certain properties with the composition, fabricating techniques, and thermal treatments found to influence them."
Date: January 20, 1960
Creator: Bradstreet, Samuel W.
Partner: UNT Libraries Government Documents Department
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Production test IP-285-C and supplement a measurement of operating temperatures of uncooled thermal shield cooling tube. Final report

Description: The iron thermal shields of the Hanford reactors are cooled by means of water flow through thermal cooling tubes embedded in the shield blocks. The flow rate, temperature rise, and allowable pressure in the tubes and the conditions under which some of the tubes may be out of service are specified in the process standards. Shield heat formation and heat transfer calculations are necessarily based on broad assumptions and are therefore usually reliable only for order of magnitude and trend predic… more
Date: July 20, 1960
Creator: Smalley, W. L.
Partner: UNT Libraries Government Documents Department
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Detection of tube leaks in piles

Description: This report discusses the use of liquid ammonia as a tracer for the detection of cooling water leaks into the piles. It is both safe and cheap and can be detected by methods adaptable to direct-reading instrumentation on a continuous-flow sample. Moderate capital costs and materials costs of less than $50 per pile test are anticipated.
Date: January 20, 1960
Creator: Upson, U. L.
Partner: UNT Libraries Government Documents Department
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Duplex bath variables experiments

Description: No Description Available.
Date: July 20, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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PT-IP-263-A-FP: Evaluation of chemically nickel plated fuel elements

Description: The objective of this test is to determine, through in-reactor testing, the resistance to corrosion of nickel plated fuel elements, plated by a chemical deposition technique. This program may eventually be composed of the following portions, the first of which is authorized by this test: (1) Irradiate ten columns of 0.5 mil chemically nickel-plated C-64 OIIN fuel elements having various heat treatments, each alternated with x-8001 control pieces. Two columns will be exposed to 400 MWD/T and eig… more
Date: April 20, 1960
Creator: Hall, R. E. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Optimum canning conditions for four-inch I & E fuel elements

Description: Because of difficulties in charging eight-inch fuel elements in bowed process tubes in the upper parts of the old reactors, IPD has requested that four-inch I & E fuel elements be provided for these tubes early in CY1961. Approximately 30,000 fuel elements of this design, Model OVN, will be required per year. Since most of these fuel elements will be charged in the upper fringe zones, they will be in-reactor for an extended period of time. For this reason, the quality of this material should be… more
Date: December 20, 1960
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Production test IP-312-A: Increase of graphite temperature limit at 105 KE and KW

Description: This production test is designed to demonstrate that the K Reactors can be operated. with a higher graphite temperature limit than stipulated in present standards without a significant increase in the rate of either burnout or contraction of the graphite moderator stack. It is intended that the increase in allowable maximum graphite temperature will be utilized to permit operation with slightly higher reactor power levels with substantially the same enrichment level of the total uranium fuel ch… more
Date: May 20, 1960
Creator: Giberson, R. C. & Benoliel, R. W.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand curves for K-reactor geometry at low tube powers

Description: The outlet water temperature limits for the Hanford production reactors are based, among other things, on the ability to prevent excessive fuel temperatures during or following inadvertent flow losses or power surges. The analyses involved in the determination of the limits are dependent upon laboratory heat transfer experiments which closely simulate actual reactor conditions in a single process tube. The heat transfer experiments are quite complex in that they involve the recording of rapid c… more
Date: July 20, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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Orifice sizes for K-reactor fringe zones with I&E fuel

Description: The purpose of this report is to describe orifice combinations which can be utilized in Zone 2, 3, and 4 of the K Reactors while using K-IV I&E fuel elements and to present working data to describe the calibration and.critical flow characteristics of initial prototypes of these orifice combinations. A discussion is included concerning the minimum flow rates attainable by front face orificing while avoiding critical flow conditions.
Date: October 20, 1960
Creator: Waters, E. D. & Calkin, J. F.
Partner: UNT Libraries Government Documents Department
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Validity of homogeneous method: Overbored vs present lattice conversion ratios

Description: A study was made to establish the validity of using homogeneous-lattice machine program calculations of the relative conversion ratio of the overbored lattice as compared to the present case. It is possible to draw both qualitative and quantitative conclusions from hand calculations utilizing simplified geometries; it is the purpose of this document to summarize such a study. Numbers included herein are not intended to represent absolute quantities, since the required calculations lie outside t… more
Date: December 20, 1960
Creator: Gilbert, W. D.
Partner: UNT Libraries Government Documents Department
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The Nitric Acid Leaching of Uranium Dioxide in a Recirculating Dissolver

Description: A brief study of the nitric acid leaching of sheared Zircaloy and stainless-steel-clad UO/sub 2/ fuels was carried out. The study was intended to demonstrate the leaching process and the use of a removable dissolver canister for transport and charge duty. In addition, the effect of sheared element length on leaching time cycles was studied. (L.T.W.)
Date: October 20, 1960
Creator: Smith, P. W.
Partner: UNT Libraries Government Documents Department
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SNAP I POWER CONVERSION SYSTEM ALTERNATOR DEVELOPMENT. Period covered: February 1, 1957 to June 30, 1959

Description: Alternator development for the SNAP 1 power conversion system is described. A radial air-gap permanent-magnet 6-pole single-phase 2600-cps alternator, rated at 536 watts, 0.8 power factor, and 115 volts was selected. Discussion of requirements and specifications, design and performance, test facilities, and conclusions are included. (J.R.D.)
Date: June 20, 1960
Creator: Morgan, H.J.
Partner: UNT Libraries Government Documents Department
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Investigation of Sodium Leak Plugging

Description: A program is reported to investigate a method of stopping sodium leaks at 1200 deg F by reacting the leaking material with a gas such as carbon dioxide or oxygen. Such a plugging mechanism would be useful in preventing shutdowns due to sodium leaks such as those in the shell of a calandria core. Results indicate little likelihood of success for this mechanism above 600 deg F. (J.R.D.)
Date: October 20, 1960
Creator: Peelgren, M. L. & McDonald, J. S.
Partner: UNT Libraries Government Documents Department
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DESIGN CRITERION OF PLENUM TO REFLECTOR BLOCK SEAL FOR HTGR REACTOR VESSEL

Description: A survey was made of sealing methods and their adaptability to the requirements of the plenum reflector seal on the HTGR reactor vessel. A leak rate through the seal of 43.8 pounds per hour of helium was established as an acceptable leak. Lap joints of steel to graphite or graphite to graphite with a 100 RMS surface finish met the required leak rate and two basic concepts of this type of seal are illustrated. (auth)
Date: April 20, 1960
Creator: Kalk, W.A.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, May 1960

Description: This document details activities of the irradiation processing department during the month of May, 1960. 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: June 20, 1960
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for May 1960

Description: Production of Pu nitrate from separations plants during May was below forecast. A Np recovery campaign in Purex yielded 1.5 kg. Production and shipments of UO{sub 3} met schedules. Unfabricated Pu metal production was below forecast, but all shipments were on schedule. Decontamination efficiency was low in Purex solvent extraction around the time of the Np recovery. The damaged Redox B-2 dissolver is being restored; processing of enriched metal in A and C dissolvers was continued. A spectrograp… more
Date: June 20, 1960
Partner: UNT Libraries Government Documents Department
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STANDARD OPERATING PROCEDURE FOR TSR-II

Description: The daily check list, the startup procedure both for in-pool and in-air operation, and the normal shutdown procedure for the Tower Shielding Reactor-II are outlined. The sequence of events which leads to each annunciator warning and the automatic corrective action which is then initiated by the control circuits are described. (auth)
Date: April 20, 1960
Creator: Lewin, J. S.
Partner: UNT Libraries Government Documents Department
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SNAP I POWER CONVERSION SYSTEM MATERIALS DEVELOPMENT. Period covered: February 1, 1957 to June 30, 1959

Description: Investigations of materials for use in connection with the SNAP I mercury Rankine cycle power conversion system are discussed. Test programs are outlined and results are tabulated for each candidate material. Several nonmetallic materials and processing procedures were developed which enabled uncooled high-performance electric machinery to operate at 550 deg F in mercury vapor. (J.R.D.)
Date: June 20, 1960
Creator: Hambor, V. F. & Owens, J. J.
Partner: UNT Libraries Government Documents Department
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SM-1--RESEARCH AND DEVELOPMENT QUARTERLY REPORT FOR APRIL 1 TO JUNE 30, 1960

Description: With the exception of a brief period of slightly elevated chloride level in the secondary blowdown, water-chemistry conditions during the period were satisfactory. During the period, the reactor was shut down for end-of-core-life testing and rearrangement. A set of specifications covering all electronic and electromechanical mechanisms required to control the SM-1 reactor through the rod- drive motors and clutches was prepared and issued. Installation of instrumentation for plant response and s… more
Date: September 20, 1960
Creator: Bergman, C. A.; Brown, W. S. & Hasse, R. A. et al.
Partner: UNT Libraries Government Documents Department
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