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Salt Bath Heat Transfer Rates for Uranium Plate

Description: Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Annual Report: 1961 - 1961

Description: Annual technical report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between February 1, 1961 to February 28, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 28, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Ground Water Test Well D, Nevada Test Site, Nye County, Nevada

Description: Introduction: The U.S. Geological Survey is appraising the possibility, however slight, that the ground water beneath the Nevada Test Site, possibly contaminated by nuclear detonations, may carry radioactive fission products to places where they may constitute a public hazard.
Date: February 9, 1962
Creator: Thordarson, William; Garber, M. S. & Walker, George E.
Partner: UNT Libraries Government Documents Department
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Eddy Transport in Liquid-Metal Heat Transfer

Description: This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.
Date: February 18, 1962
Creator: Dwyer, Orrington Embry, 1912-
Partner: UNT Libraries Government Documents Department
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Metabolism of C¹⁴-Carboxyl-Labeled-3-Hydroxyanthranilic Acid in Normal and Neoplastic Mice

Description: The o-aminophenol, 3-hydroxyanthranilic acid (3-OHAA) is a metabolite of tryptophan normally present in urine in trace quantities. C14-3-OHAA was given to normal mice and mice with either mammary adenocarcinoma, glioblastoma multiforme or ascites tumor to study the influence of these transplantable tumors on metabolism of 3-OHAA.
Date: February 16, 1962
Creator: Hankes, Lawrence Valentine; Schmaeler, Max & Stoner, Richard D.
Partner: UNT Libraries Government Documents Department
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Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Light Buoy, SNAP-7A

Description: From introduction: A prototype Strontium-90 fueled generator will be used to fulfill the power requirements of an unattended automatic light buoy...Primary objectives are to provide continuous absolute containment of the radiostrontium fuel...and biological shielding of the direct radiation from the heat source.
Date: February 1962
Creator: Brooks, Phillip M. & Keegan, James J.
Partner: UNT Libraries Government Documents Department
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Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: January 1962

Description: This is the seventeenth progress report in this study recording progress made in areas such as the receival of new Cr-Mo specimens that are scheduled to be tested during the next report period, various testing operations for Loops 1 and 2 fatigue, creep, and stress tests in sodium, and the discontinuation of a 316 ss specimen in air at 1200 F to examine the specimen and review the data.
Date: February 13, 1962
Creator: King, E. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
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Technical Specifications: Hanford Production Reactors. Revision 4

Description: This report provides technical specifications applicable to the eight operating production reactor facilities, namely B, C, D, DR, F, H, KE and KW (referred to as the Hanford Production Reactors), located at the Hanford Site in the State of Washington. Basic descriptions of the reactor facilities are also contained in the report.
Date: February 16, 1962
Creator: Gilbert, W. D.
Partner: UNT Libraries Government Documents Department
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River contamination reduction studies an evaluation of the artificial lake concept

Description: Currently the Irradiation Processing Department is working on a program which has as its goal the reduction of radioactive discharge to the Columbia River. The most significant radioactive isotopes of concern are the relatively long lived isotopes P{sup 32}, Zn{sup 65}, As{sup 76}, N{sub p}{sup 239} and Cr{sup 5l}. Because of their relatively long life they can be found in the Columbia River well below the Hanford Plant. P{sup 32}, because it is absorbed and concentrated by the river biota is o… more
Date: February 26, 1962
Partner: UNT Libraries Government Documents Department
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Summary status report internal corrosion of ribbed aluminum process tubes

Description: The increasing incidence of leaking process tubes, and the approaching end of the useful life of process tubes in the C and K Reactors, have focused attention upon the various sources of aluminum process tube leaks. Further, the replacement of large numbers of process tubes with new ones, also of aluminum, will require continued attention to these sources to make efficient use of the new tubes. One of the sources of process tube leaks is the corrosion that attacks the interior surface of the pr… more
Date: February 19, 1962
Creator: Carlson, P. A.; Curtiss, D. H.; Miller, N. R. & Van Wormer, F. W.
Partner: UNT Libraries Government Documents Department
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Rear crossheader expansion joints

Description: The purpose of this report is to describe the results of prototypic tests of piping alterations designed to alleviate the above described conditions and to outline a program for full-scale implementation of these alterations.
Date: February 8, 1962
Creator: Hutton, P. H.
Partner: UNT Libraries Government Documents Department
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Reactor process flow technical data

Description: A computer program is being developed for the solution of general system flow problems. As a complement to this program, a summary of the process system has been prepared. This assembles information from a number of different reports, drawings and technical notebooks into one place for easy use and reference. It is expected that the information contained in this report will be of use in safety and design studies of these process systems. This report presents current values of the reactor flow c… more
Date: February 15, 1962
Creator: Jones, S.S.; Morrissey, J.E. & Manuel, J.L.
Partner: UNT Libraries Government Documents Department
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KER loop fuel testing program and schedule, CY 1962

Description: The interests of several departments at Hanford are involved in the planning, execution and evaluation of the results of the KER loop testing effort in support of the NPR fuel program. The varied interests and activities of the participating groups must be well-integrated if effective use of our limited testing capability is to be made. The purpose of this report is to help achieve this integration by summarizing the current thinking on the goals of the NPR fuel testing program and by presentin… more
Date: February 14, 1962
Creator: Evans, T.W. & Kratzer, W.K.
Partner: UNT Libraries Government Documents Department
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Production test IP-466-A test of the 190 turbine pumps at KE(KW) Rector (Project CGI-844)

Description: The purpose of this test is to provide for adequate testing of the new steam turbine pumps. This will cover the tests required for the acceptance of these new items as per ATP-2588 and for any additional testing required to ensure reactor emergency cooling adequacy and reliability. A further objective is to provide the safety requiring by which the objectives of the ATP-2588 may be accomplished. A steam pump is being installed in each of the 190-K buildings to provide an additional secondary su… more
Date: February 1, 1962
Creator: Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Numerical results of PT IP-412-AI, B and C reactors export system test

Description: The purpose of this document is to present the numerical results of a production test of the last ditch water backup system performed at B and C reactors on December 15, 1961. The main purpose of the production test was to determine more accurately the capacity of the export system for supplying flow to a dual reactor area under several simulated emergency conditions where BPA power to all areas has been interrupted and the steam supply to one old area has been lost. In addition, the flow capac… more
Date: February 20, 1962
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
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Graphite distortion ``C`` Reactor. Final report

Description: This report covers the efforts of the Laboratory in an investigation of the graphite distortion in the ``C`` reactor at Hanford. The particular aspects of the problem to be covered by the Laboratory were possible ``fixes`` to the control rod sticking problem caused by VSR channel distortion.
Date: February 8, 1962
Creator: Wood, N. H.
Partner: UNT Libraries Government Documents Department
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Results of Ten Tube Operational Fueling on February 9, 1962

Description: Ten columns of ripe uranium were discharged and recharged from KE Reactor during operation (first large scale refueling test with Operational Fueling Facility gear). For the last year, many tests were performed in preparation for the ten tube discharge. Objectives of the production test have been met. The system was proved to be feasible; no reactor control problems were encountered by refueling during operation.
Date: February 15, 1962
Creator: Hammond, R. S.; McCarthy, P. B. & Hawkins, K. G.
Partner: UNT Libraries Government Documents Department
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Prerequisite requirements for higher graphite temperature limits and/or nitrogen atmosphere at all reactors

Description: The graphite temperature limits specified in the process standards-are being closely approached or have limited power levels at B, D, DR, and reactors. An increase of approximately 50--100 C in graphite temperature limits at these reactors would permit year-around operation on bulk outlet temperature limits. There has been considerable recent interest in extending to all reactors the use of nitrogen as a reactor gas constituent. With present graphite temperature limits, significant benefit from… more
Date: February 26, 1962
Creator: Graves, S. M.
Partner: UNT Libraries Government Documents Department
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