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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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Process Vessel Precision and Accuracy Estimates

Description: The following is an attempt to explain the method by which the precision associated with an observed volume reading in a process vessel (E-12, C-1) should be calculated based upon a regression analysis of cumulative data. There are two types of volume measurement consists of estimating the total volume in a vessel at some inventory time. A transfer measurement consists of estimating the volume between two levels within a tank.
Date: March 2, 1959
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department
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Artificial Cooling of the Columbia River By Dam Regulation Part 1

Description: In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date: May 25, 1959
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Manual of Radiation Protection Standards

Description: "The following is an alphabetical listing of terms and units in common usage at HAPO. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date: July 1957
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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"Crud" Scrubbing with a Purex-Type Zebra Cartridge

Description: Entrained solids have in the past been one of the major factors limiting solvent extraction fission product decontamination. These solids are known to be surface active, to absorb fission products, and to form interfacial films or "cruds". A major step in eliminating these cruds was taken when the Purex columns were modified to operate with the interfaces at the waste ends of the columns rather than the product ends. This type of operation tended to flush the solids out with the waste rather th… more
Date: October 17, 1961
Creator: Richardson, G. L
Partner: UNT Libraries Government Documents Department
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Once Through Decontamination Studies- Interim Report No. 1.

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has also been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This report contains information on a series of tests performed in the 242-B single pass flow facility. Information concerning the following are presented: (1) Efficiency of decontaminating KER Loop 1 and 2 contaminated specimens. (2) Efficiency of… more
Date: January 12, 1960
Creator: Perrigo, L. D. & Hekenson, J. F.
Partner: UNT Libraries Government Documents Department
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Corrosion of Stellite in MJ-1 Streams

Description: The following report provides data from completed tests for corrosion testing of stellite-T347 stainless steel test cylinders.
Date: March 8, 1950
Creator: Koenig, W. W.
Partner: UNT Libraries Government Documents Department
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HAPO IB Fission Product Shipping Cask Design Evaluation Report

Description: As a result of the interest in fission products for use as heat sources and/or radiation sources, in early 1960. Hanford was authorized to supply a semi-refined cerium-144 rare earth product to Oak Ridge National Laboratories. Facilities were installed for collecting this product and a cask war designed for shipping this product as a stabilized, dry powder. Since that time, numerous improvements have been made in the design of the HAPO I cask as described in Revision O of this document. In add… more
Date: December 28, 1962
Creator: Smith, C. W.
Partner: UNT Libraries Government Documents Department
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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 the transient cases. The question… more
Date: April 18, 1960
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959

Description: One of the primary reasons for operating the high pressure KER loops is to obtain information concerning water quality control characteristics for recirculating water cooled reactors. The KER-1 loop is predominantly carbon steel and approximates the water quality conditions specified for the New Production Reactor (NPR).
Date: June 15, 1960
Creator: Demmitt, T. F. & Wood, E. R.
Partner: UNT Libraries Government Documents Department
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Parian and Teflon in 1A Redox Solutions

Description: This report analyzes Parian and Teflon that were exposed to solutions of 1AX, 1AS, and 1AF, ANL June 1, 1948 Flowsheet, under conditions described in the following report.
Date: May 9, 1949
Creator: Koenig, W. W.
Partner: UNT Libraries Government Documents Department
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General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948

Description: Introduction: "This report covers progress on the testing of the General Engineering and Consulting Laboratories Turbine Pump No. 1 from May 1, 1948 to Jun 15, 1948. All testing prior to April 30, 1948 has been described in Redox Experiment Testing Report No. 1 (Document HW-9474) and No. 2 (Document HW-9694)."
Date: June 21, 1948
Creator: Stringer, J. T. & Allen, A. W.
Partner: UNT Libraries Government Documents Department
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Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs

Description: Abstract: "A batch of slugs is being prepared for which the U-235 content will be 1.75 per cent, and it is of interest to calculate the minimum number of such slugs required for a critical assembly in water. Using Handbook (CL-697) methods, a critical assembly of these slugs arranged in a lattice with a spacing of 5.5 cm."
Date: September 11, 1952
Creator: Erkman, John O.
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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The Ratio of Plutonium 239 to Uranium 235 Fission Cross Sections from 0.020 to 1.0 Electron Volts

Description: Foils of plutonium 239 and uranium 235 have been mounted back to back in a dual ionization fission chamber in the diffracted beam of the Hanford neutron crystal spectrometer. A quantity proportional to the ration of fission cross sections of Pu239 to U235 has been measured as a function of neutron energy from 0.020 to 1.0 electron volts. The results of this investigation are presented graphically in the text.
Date: December 1, 1953
Creator: Leonard, B. R., Jr.; Hauser, S. M. & Seppi, E. J.
Partner: UNT Libraries Government Documents Department
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Plating Thickness Tester

Description: An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Date: November 15, 1957
Creator: Fitch, C. E., Jr.
Partner: UNT Libraries Government Documents Department
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Clarification of Redox Feed (1AF) by Filtration : A Semi-Works Study Progress, Redox Technical Data Study No. 8

Description: The following report was made to determine the effective clarity improvement, flow rate characteristics, and operational problems encountered on passing Redox uranium feed solution through sintered, modified Type 304 stainless steel filter elements.
Date: October 15, 1948
Creator: Cooper, V. R. & Coleman, E. M.
Partner: UNT Libraries Government Documents Department
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Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Description: Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.
Date: December 1962
Creator: Defferdin, L. J.
Partner: UNT Libraries Government Documents Department
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