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3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples

Description: The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors… more
Date: October 22, 1959
Creator: Moulthrop, H. A.
Item Type: Refine your search to only Report
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709 Program for Reduction of Exponential Pile Data

Description: A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date: August 20, 1959
Creator: Matsumoto, D. D.
Item Type: Refine your search to only Report
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1706 KE Water Treatment for Out-of-Reactor Test Facilities.

Description: Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date: March 30, 1959
Creator: Demmitt, Thomas F.
Item Type: Refine your search to only Report
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Accuracy of Volume Measurements in a Large Process Vessel

Description: The Non-Production Fuel Reprocessing Program involves the chemical processing of valuable reactor fuels received from privately owned power reactors. It is necessary therefore, to accurately measure the fuel material received in order to insure proper payment to reactor operator and to provide the Atomic Energy Commission with appropriate accountability data. The volume measurement study described herein was conducted in order to determine the limits of accuracy that could be obtained in measur… more
Date: October 19, 1959
Creator: Pleasance, C. L.
Item Type: Refine your search to only Report
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All In-Well Permeability Testing Packer

Description: Disposal of liquid radioactive wastes to ground requires knowledge of the area ground-water hydrology. Information is desired on direction and velocity of ground-water flow. Direction of flow can be determined from maps showing contours on the water table surface, such contours being derived from well water elevations. Ground-water velocity is more difficult to ascertain.
Date: September 29, 1959
Creator: Raymond, J. R.
Item Type: Refine your search to only Report
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Analysis of a Nuclear Incident in a Redox Dissolver

Description: Since the start of E-metal processing in December, 1958, critical mass control in the Redox dissolvers has been provided by a combination of administrative controls, revised dissolver charging procedures, and new dissolving processes and operation control procedures. These were all based on a maximum allowable charge of E-Metal to the dissolvers which was equivalent to 45 percent of the minimum critical mass.
Date: August 24, 1959
Creator: Neely, V. I.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels

Description: A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date: December 1, 1959
Creator: Goffard, J. W.
Item Type: Refine your search to only Report
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An Automatic Water Deaeration System

Description: Laboratory studies involving fluid flow through porous media require use of fluids having low dissolved gas content. Water is the major fluid used in various and box model and soil permeability studies carried out by the Geochemical and Geophysical Research group. Tap water supplied to the 222-U Bldg. contains a large amount of dissolved air. Under the reduced pressure encountered during model studies, the air is released from solution and gradually clogs the pores of the sand or other porous m… more
Date: April 20, 1959
Creator: Raymond, J. R.
Item Type: Refine your search to only Report
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Chemical Reactivity of Uranium Monocarbide and Uranium Mononitride with Water at 100°C.

Description: The monocarbide and the mononitride of uranium are potentially useful ceramic nuclear fuel materials. This paper reports the results of exploratory investigations of the reactions of uranium monocarbide and uranium mononitride with boiling water. Uranium dioxide, chemically stable in deoxygenated boiling water, was used as a control.
Date: February 26, 1959
Creator: Newkirk, H. W.
Item Type: Refine your search to only Report
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A Closed Circuit Television System for In-Well Use -- Interim Report

Description: Wells drilled to date on the Hanford project represent and initial investment of over one million dollars. These nearly six hundred wells have been used and will continue to be used for observation and monitoring purposes of direct interest to ground disposal of radioactive wastes. Through measurement of depth to the water table the changing gradients as a result of large volume waste disposal are determined and direction of ground water flow established. The extent of contamination in ground … more
Date: August 5, 1959
Creator: Ratcliffe, C. A.
Item Type: Refine your search to only Report
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Comments on Engineering Review of PRTR by Atomic Power Equipment Department

Description: On a project of the magnitude and complexity of the Plutonium Recycle Test Reactor is was considered prudent engineering practice to obtain an independant design review by a competent off-site group that had not participated in any way in the development of the design. Accordingly, the Atomic Power Equipment Department of the General Electric Company was requested to make such an engineering review, and an Assistance to Hanford contract authorizing this work was approved by the Atomic Energy Co… more
Date: October 15, 1959
Creator: Reactor and Fuels Researcg and Development Operation Hanford Laboratories Operation
Item Type: Refine your search to only Report
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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Item Type: Refine your search to only Report
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Composition of Solids from Purex LWW

Description: The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww tha… more
Date: January 22, 1959
Creator: Van Tuyl, H.H.
Item Type: Refine your search to only Report
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Computational Aids for Estimating Performance of Liquid to Boiling Water Heat Exchangers

Description: The computation of liquid-boiling heat exchanger performance under a wide variety of operating conditions is a cumbersome, time-consuming procedure. Rapid evaluation of a design requires the use of some form of computational aid. Exchanger equations covering the case of liquid-boiling heat transfer have been derived and evaluated for a specific correlation of local boiling condition. Examination of various data as presented by Bonilla and McAdams indicates that the boiling coefficients are not … more
Date: September 1, 1959
Creator: Love, W. J.
Item Type: Refine your search to only Report
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Concentration and Final Purification of Neptunium by Anion Exchange

Description: It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless s… more
Date: February 10, 1959
Creator: Ryan, J.L.
Item Type: Refine your search to only Report
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Confinement System Instrumentation

Description: Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date: November 6, 1959
Creator: Richards, W. A.
Item Type: Refine your search to only Report
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Continuous Ion Exchange Development - A Qualitative Review

Description: Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facili… more
Date: November 10, 1959
Creator: Nicholson, G. A.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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Corrosion Equipment Prototype

Description: A new package type facility for corrosion decontamination studies has been designed and fabricated. This report gives a description, drawings, and comments on its operation. It has been in operation since December, 1958.
Date: June 9, 1959
Creator: Neibaur, G. E.
Item Type: Refine your search to only Report
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