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AN INFORMATION STORAGE AND RETRIEVAL SYSTEM FOR IRRADIATION EFFECTS IN METALS

Description: An information storage and retrieval system (PIC) was developed, utilizing the IBM 7090 computer, for handling data pertaining to the effects of neutron irradiation on metals. The input includes a reference identification, an appropriate abstract or extract summarizing the article, code identification parameters analogous to those used by the ASM-SLA Literature Classification System, and special codes identifying relevant irradiation and testing parameters. The output contains the same data plus printing out the meaning of all special codes. Presently, the information storage consists of more than two hundred references representing several thousand lines of information. The system is both general and definitive, permitting the selection of a single piece of information or of many references dealing with a general field. It is possible to select material on the basis of one or more of the following factors: material, general or specific; type of literature; general or specific property such as mechanical tests or tensile tests; conditions of irradiation including type and level of flux, integrated flux, irradiation temperature, and reactor environment; test conditions such as temperature and environment; and general variables that might be controlling such as strain rate, specimen geometry, grain size, and fabrication history. It is felt that this system and the data systems will permit the rapid selection of relevant references once an optimum number of such references are available. (P.C.H.)
Date: August 15, 1963
Creator: Bush, S. H.
Partner: UNT Libraries Government Documents Department
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Reactor statistics, Section III, April 1961--May 15, 1962. Reactor 3

Description: The discussion and summary report presented here illustrate the type of information that is currently in data processing machine language and available to those who require it. During the progress meetings at which these reports were discussed, several persons indicated a desire to have a documented explanation of the report and a personal copy to scan. This is the answer to these requests. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest.
Date: June 13, 1962
Creator: Burke, R.C.
Partner: UNT Libraries Government Documents Department
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Status report of irradiated NPR fuel element rupture studies in the IRP

Description: The Irradiated Rupture Prototype (IRP) has been used for rupture testing irradiated NPR prototype fuel elements. Most of the tests have been made to determine the rupture effect of different reactor exposures, fuel element geometries and water cooldown rates following the start of the rupture. This report summarizes the results obtained to date, mentions where information is lacking and gives further tests scheduled for the IRP.
Date: September 9, 1963
Creator: Hayden, K.D.
Partner: UNT Libraries Government Documents Department
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Reactor statistics, Section III, April 1961--May 15, 1962. Reactor Simulation Study, Reactor 5

Description: The discussion and summary report presented here illustrate the type of information that is currently in data processing machine language and available to those who require it. During the progress meetings at which these reports were discussed, several persons indicated a desire to have a documented explanation of the report and a personal copy to scan. This is the answer to these requests. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest.
Date: June 13, 1962
Creator: Burke, R.C.
Partner: UNT Libraries Government Documents Department
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Precipitation of cerium sulfate

Description: Cerium sulfate purified by D2EHPA in Semiworks can be precipitated by adjusting pH to between 1 and 2 in tank 6 with 50% caustic. The solution can then be transferred through tank 1 to tank 67, where sodium bisulfate is added to make the solution 0.5M sulfate. A stoichiometric amount (mole for mole) of 50% caustic is added to just neutralize the sodium bisulfate. The precipitate is digested one hour at 60 C, then filtered.
Date: January 27, 1964
Creator: Buckingham, J. S.
Partner: UNT Libraries Government Documents Department
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Probability of ruthenium reduction in H-4 by self-radiation

Description: The following calculations have been made at the request of H.R. Schmidt to determine the probability that self-radiation may play a substantial role in the decomposition of the ruthenium tetroxide in the reflux scrubber, section of the Redox Ruthenium Oxidizer (H-4). The validity of the derived data necessarily depends upon the correctness of the basic assumptions made with regard to process conditions and to possible radiation-activated mechanisms of disintegration. It is estimated that the extent of solid ruthenium formation in the tower which results from radiation effects should not exceed 100 micrograms per batch. This rate is negligible compared to that now found in the presence of stainless steel packing, or to that which might be expected from thermally-activated disintegrations alone.
Date: June 8, 1954
Creator: Upson, U. L.
Partner: UNT Libraries Government Documents Department
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Redox Plant shutdown, January 8, 1955--February 2, 1955

Description: This report summarizes work completed during the Redox Plant shutdown in January 1955. An analysis of major difficulties encountered, improvements made during the shutdown, and building design deficiencies brought to light by the shutdown are discussed. (JL)
Date: February 15, 1955
Partner: UNT Libraries Government Documents Department
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Fallout concentrations of 12 radionuclides in air: 1962 through mid-1964

Description: Newly developed multidimensional gamma-ray spectrometric counting techniques permit the direct measurement of twelve fallout radionuclides on air filters. Observed concentrations of Be{sup 7}, Na{sub 22}, Mn{sup 54}, Co{sup 60}, Y{sup 88}, Zr{sub 95}Nb{sup 95}, Ru{sup 106}, Sb{sup 124}, Sb{sup 125}, Cs{sup 134}, Cs{sup 137} and Ce{sup 144} during the past two and a half years help explain the origin and fallout rates of the trace radionuclides in air. 14 refs., 1 tab.
Date: June 17, 1964
Creator: Perkins, R. W.; Nielsen, J. M. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
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Review of effluent disposal practices in N Reactor Department

Description: A survey has been conducted of current methods of disposal of radioactive, chemical, and sanitary wastes used both at the 100 Area and 300 Area sites of N Reactor Department Operations. In addition, liquid storage facilities have been surveyed for situations which might result in river water pollution. The survey and this report have been prepared in response to the request of the Manager, Richland Operations Office of the Atomic Energy Commission in accordance with Executive Order 11258. An audit of N Reactor Department waste disposal procedures and practices was recently made. The audit report provides detailed data on effluent streams, methods,d and sampling points. Therefore, this report does not include that information and instead provides a summary of experimental and analytical data which have become available since the audit. It also includes information developed in response to specific provisions set forth in the Executive Order.
Date: February 28, 1966
Creator: Stepnewski, D. D. & Hendrickson, M. M.
Partner: UNT Libraries Government Documents Department
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Radioactive contamination in liquid wastes discharged to ground at the separations facilities through December 1962

Description: This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1962. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December 1962. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1962. Tables list the major disposal sites in the separation facilities, total volume of waste discharged to each location, and the gross amounts of plutonium and beta particle emitters discharged to ground since startup. This same data is presented on a monthly basis for cribs still in use. Information is presented on the source of the waste stream and the settling facility if used. Isotopic data are included for disposal sites from which the waste was analyzed for specific contaminants. Estimates of contamination and volumes discharged to swamps are also included.
Date: March 12, 1963
Creator: Backman, G. E.
Partner: UNT Libraries Government Documents Department
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Production Test No. 105-511-A -- Irradiation of stainless steel samples

Description: This study soughs to determine the x-ray activity of two samples of stainless steel prepared from tubing used in the ANL-140, in-pile experiment (P-13). This information is necessary in order to predict the activity of the P-13 rig at the time of removal. The primary contribution to the over-all activity will be from Ta{sup 181} and Co{sup 59} impurities.
Date: April 2, 1952
Creator: Gillard, C. W.
Partner: UNT Libraries Government Documents Department
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Flowsheet No. 1: Cesium isolation and packaging

Description: An engineering flowsheet has been prepared for the conversion of an aqueous slurry of cesium-zinc-ferrocyanide into a dry cesium chloride product by the calcination process. Flowsheet No. 1 defines a six-step batch-type calcination operation for processing the slurry into a dry powder for offsite shipment in bulk containers. Some of the advantages to this process are as follows: Product losses are expected to be small, estimated to be less than 0.03 percent; the equipment required to process a given number of curies per batch appears to be relatively small, compact, and simple; the process does not impose severe requirements for materials of construction; and requirements for process control and instrumentation are expected to be simple. There are two disadvantages to this process. First, the cesium-zinc-ferrocyanide precipitate is not considered economically filterable, hence, the separation of solids from liquids is encumbered. Second, the process, as outlined, if potentially hazardous because of the possible nitrate carry-over with the influent slurry. This nitrate may cause a rapid reaction in the calcination step. It is concluded that this flowsheet offers a satisfactory scheme for isolating radiocesium if the process is modified to preclude the possibility of nitrates or other unwanted oxidants from reaching the calcination step. 1 fig.
Date: May 20, 1957
Creator: Wirta, R. W. & Koski, O. H.
Partner: UNT Libraries Government Documents Department
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Discussion of ruthenium problem in Redox Plant

Description: A meeting was held February 5, 1954 in the 2704-Z Building to discuss the ruthenium problem in the Redox Plant and to decide on a course of action to correct the problem. The following persons were in attendance.
Date: February 8, 1954
Creator: Mobley, W. N.
Partner: UNT Libraries Government Documents Department
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Status of plant assistance irradiations as of July 16, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure received by the sample is left to the customer.
Date: August 3, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
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Results of a test of sampling in I{sup 131} plumes

Description: On September 13 and 14, 1962, 8.3 curies of iodine-131 were emitted from the Hanford Redox Plant at a rate of from 0.35 to 0.65 curies per hour for a period of approximately 18 hours. During the emission, the plume trajectories were plotted from meteorological data and samples were collected across the predicted plume trajectories at several altitudes and at distances up to 50 miles from the Plant. Filter, charcoal trap, and air samples were collected during the emission using aircraft; and caustic scrubber, vegetation, and milk samples were collected during and after the emission at selected ground stations in the usual manner. Appropriate background samples were collected before the test began. The data and conclusions are given in this report.
Date: April 18, 1963
Creator: Brouns, R. J.; Fuquay, J. J.; Simpson, C. L.; Soldat, J. K.; Brauer, F. P. & Perkins, R. W.
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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