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Savannah River Plant 200 Area technical manual. Part SP. Processing of Np/sup 237/ and Pu/sup 238/

Description: This manual covers the technology involved in the 200 Area process for the recovery of Np/sup 237/ from certain aqueous waste streams in the separations plants, for the recovery of NP/sup 237/ and Pu/sup 238/ from irradiated NpO/sub 2/-Al slugs and for the fabrication of NpO/sub 2/-Al slugs. The manual contains sections on the fundamental chemistry, the primary recovery of Np by ion exchange, the decontamination of Np by ion exchange, the processing of NpO/sub 2/-Al targets, the separation and … more
Date: January 3, 1963
Creator: Hill, A.J. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical decontamination of Hanford production reactors

Description: The conduct of outage work in the discharge areas of the Hanford production reactors has always been complicated by personnel exposure to radiation from the contaminants which accumulate in the effluent water piping in the course of normal operations. These containments represent trace impurities in the cooling water, together with corrosion products, which are irradiated in passing through the reactor and then deposit in the unshielded rear face piping. Radioactive residues also accumulate on … more
Date: June 27, 1963
Creator: Hauff, T. W.; Jensen, H. F. & Smith, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LABORATORY INVESTIGATIONS IN SUPPORT OF FLUID-BED FLUORIDE VOLATILITY PROCESSES. PART II. THE PROPERTIES OF PLUTONIUM HEXAFLUORIDE

Description: All of the properties of plutonium hexfluoride reported up to May 1983 are summarized, andd pentinent data are presented in detail. Included are the preparation of plutonium hexafluoride, physical properties, absorption spectra, chemical reactions, decomposition of plutonium hexafluoride by radiation and heat, the corrosion of materials of construction by plutonium hexafluoride, and a summary of the biological and radiological hazards from plutonium hexafluoride. An expanded vapor pressure tabl… more
Date: August 1, 1963
Creator: Steindler, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Organic Coolant Research Summary Report, July 1, 1960-March 31, 1963

Description: : : 7 : ; : = : : 9 ; 8 : ; / he use of organic liquids as reactor moderator-coolants is presented. A major part of the study was devoted to the mechanism of radiolytic damage to coolants. A mathematical treatment for handling information on the relative reactivity of different positions on an aromatic ring was developed in some detail. Determinations on products from the radiolysis of terphenyls, biphenyl, and mixtures of these with benzene indicate that free radicals may be the main reactive … more
Date: October 1, 1963
Creator: Hillyer, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-Irradiation Evaluation of a Plate-Type UO$Sub 2$ Fuel Element

Description: The premature failure of fuel Element M22, which had six compartments of 0.100-in.-thick, 96% TD UO/sub 2/ + 6 wt% ZrO/sub 2/ fuel, was attributed to the large irradiation-induced solid volume swelling of the UO/sub 2/ fuels. This volume swelling was the result of incomplete homogenization during fabrication of the mixed and sintered U/sup E/O/sub 2/ and U/sup N/O/sub 2/ fuel s in Element M22. In addition, heavy hydriding of the Ni-free Zircaloy-2 cladding occurred in the relatively hot areas a… more
Date: January 1, 1963
Creator: Meieran, H. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Peroxide-Inhibited Decontamination Solutions for Carbon Steel and Other Metals in the Gas-Cooled Reactor Program. Progress Report, November 1959-July 1962

Description: A search for solutions suitable for dissolving uranium dioxide powder or lumps and yet noncorrosive enough to be used for decontaminating the carbon steel EGCR charge and service machines resulted in the development of buffered oxalate solutions of controlled temperature and pH, with hydrogen peroxide added to act as corrosion inhibitor, UO/sub 2/ oxidizer, and decontamination aid. Hydrogen peroxide acts either as a corrosion promoter or inhibitor, depending on factors such as its concentration… more
Date: January 1, 1963
Creator: Meservey, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Demonstration of the Zirflex and Sulfex Decladding Processes and a Modified Purex Solvent Extraction Process, Using Irradiated Zircaloy-2 and Stainless-Steel-Clad Urania Specimens

Description: The Zirflex and Sulfex processes for chemical decladding Zircaloy or stainless-steel-clad UO/sub 2/ power reactor fuels were successfully demonstrated at irradiation levels as high as 28,200 Mwd/t. The Zircaloy jackets were dissolved in boiling 6 M NH/sub 4/F-- 1 M NH/sub 4/NO/sub 3/, and the stainless steel jackets were dissolved in refluxing 4 M H/sub 2/SO/sub 4/. Both processes gave average soluble losses of uranium and plutonium to the decladding reagents of about 0.05%. Centrifugation or f… more
Date: May 23, 1963
Creator: Goode, J.H.; Baillie, M.G. & Ullmann, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SMALL-SCALE DEMONSTRATION OF THE MELT REFINING OF HIGHLY IRRADIATED URANIUM- FISSIUM ALLOY

Description: Five melt refining demonstration experiments were conducted with highly irradiated EBR-II prototype fuel to verify earlier data on fission product removals obtained with unirradiated and lower-activity alloys. In each experiment, approximately 0.4 kg of uranium-fissium fuel pins irradiated to burnups ranging from 0.22 to 1.75 total atom percent was melt refined for 1 or 3 hr at 1400 C in a limestabilized zirconia crucible. The behavior of fission products was consistent with the earlier results… more
Date: August 1, 1963
Creator: Trice, V.G. Jr. & Steunenberg, R.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ARMY REACTORS PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING OCTOBER 31, 1962

Description: ; 8 7 < 8 < : : : 6 9 9 = < 9 < : 5 < > ;" icipation in the program continued to include review, inspection, and support in various areas of reactor technology. An advanced fuel irradiation test program was established that is to be conducted in the pressurized-water loop in the Oak Ridge Research Reactor. Review of the design of the MH-1A reactor was initiated. This reactor, a pressurized-water system fueled with low- enrichment bulk UO/sub 2/ clad with stainless steel, is being designed as a … more
Date: April 10, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transuranium Quarterly Progress Report for Period Ending August 31, 1962

Description: TRANSURANIUM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING AUGUST 31, 1962 On Process Development, Equipment Development, HFIR Target Fabrication Process Development, Design Studies, Materials Evaluation Studies, TRU Corrosion Studies, Analytical Development and Uranium-232 Preparation. (auth)
Date: February 1, 1963
Creator: Ferguson, D.E. comp.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

RADIOISOTOPE-FUELED POWER SUPPLIES. Lecture Presented at University of California, Los Angeles, California, UCLA Short Course, Space Power Systems, July 17-28, 1961

Description: Considerations that permit selection of a radioisotope that meets the complex requirements of the desired power supply are discussed. Methods of separation and purification of useful isotopes are outlined. Brief mention is made of the principles of direct conversion of heat to electricity. Design approaches for isotopic power units are described. A delineation of the approach to the solution of the nuclear safety problem is made, followed by predictions for the future of isotopic power. Sample … more
Date: October 31, 1963
Creator: Morse, J.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Elk River Reactor Technical Specifications

Description: The technical specifications that govern the design and operation of the Elk River Reactor plant are presented. Design specifications of physical features of the facility and limitations governing operations of the facility to be observed by operating personnel are included. Topics covered include: site, containment, primary coolant system, primary coolant auxiliary systems, secondary coolant system, reactor core, control and safety systems, radiation monitoring systems, waste disposal systems,… more
Date: July 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tests of High-Efficiency Filters and Filter Installations at ORNL

Description: High-efficiency filters are used in air-handling systems as the primary means of minimizing the amount of radioactive particulate matter released to the atmosphere. The filtration efficiency is successfully measured in situ using an aerosol of dioctyl-phthalate and a forward light scattering photometer. Tests are made to determine the linearity of the Naval Research Laboratory type photometer, the precision of filter efficiency determinations, the effect of prolonged exposure to aerosol on filt… more
Date: June 1, 1963
Creator: Parrish, E.C. & Schneider, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Mechanical Neutron Filter for a Crystal Spectrometer

Description: A velocity selector of the Dash-Sommers type with straight slits was constructed for use with the MTR crystal spectrometer. The rotor, designed to remove undesirable higher order contaninants from the Bragg beam, is built of magnesium and fiberglas-epoxy laminate to minimize weight and is driven directly by a 1/8-hp synchronous motor. Vanes of fiberglas laminate are set into 235 slots milled around the periphery of a 4'' diameter magnesium core. High strength is attained by winding the assemble… more
Date: June 14, 1963
Creator: Smith, J. R. & Miller, H. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LOW-RADIOACTIVITY-LEVEL WASTE TREATMENT. PART I. LABORATORY DEVELOPMENT OF A SCAVENGING-PRECIPITATION ION-EXCHANGE PROCESS FOR DECONTAMINATION OF PROCESS WATER WASTES

Description: A scavenging-precipitation ion-exchange process using phenolic resins was developed to decontaminate lowradioactivity-level process water waste prior to discharge to the environment. In laboratory and small engineeringscale tests, greater than 99.9% of the cesium and strontium, the principal biological hazards were removed from ORNL low-level waste, and the total activity level was lowered to less than the maximum permissible concentration recommended for populations in the neighborhood of atom… more
Date: July 10, 1963
Creator: Holcomb, R.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A FACILITY FOR THE PRODUCTION OF Pu$sup 238$

Description: A pilot plant facility for recovering Pu and unconverted neptunium from irradinted neptunium target elements was operated for 17 months at the Savannah River Laboratory. The process required that the irradiated target elements be dissolved and the solution be processed through three anion exchange cycles for removal of undesirable fission products and cations, recovery of unconverted neptunium, and concentration of the Pu/sup 238/ solution. The process equipment was enclosed in three stainless … more
Date: July 1, 1963
Creator: Tetzlaff, R.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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STANDARD DESIGN CRITERIA

Description: Hanford Atomic Production Operation specification gaides for design criteria, structural engineering, civil engineering, heating, ventilation, air conditioning, fire alarm systems, noise control, lighting, railroad construction, corrosion protection, and electrical engineering are presented. Details of this manual are given in TID-4100 (Suppl.). (N.W.R.)
Date: January 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Apparatus for the Gasometric Study of Solid-Gas Reactions: Sodium Fluoride With Hydrogen Fluoride and Uranium Hexafluoride

Description: A gasometric apparatus for rapidly characterizing dissociation pressures, sorption equilibrium and kinetics, chemical states, and decomposition conditions was built and tested. The method involves the measurement of quantities of gases reacting with or evolving from known quantities of solid. Accuracies of better than plus or minus 1% were attained. In testing the capabilities of tue apparatus, the dissociation pressures of hydrogen fluoride and uranium hexafluoride over their respective comple… more
Date: October 29, 1963
Creator: Katz, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROGRESS IN TREATMENT OF A RADIOACTIVE CONDENSATE WASTE

Description: A waste stream decontamination process based on ion exchange was selected for development. The process is centered on ion-exchange technology developed during recent years in the Hanford Laboratories and other atomic energy research centers. Early attempts at small engineering scale application of ion- exchange technology resulted in less than satisfactory results when compared to laboratory data. The difficulties were traced to nonradioactive impurities in the wastes. Steam stripping and filte… more
Date: October 1, 1963
Creator: Skarpelos, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mound Laboratory Progress Report for September 1963

Description: Three silicone-based conductive adhesives were formulated and evaluated. One of the formulations had a resistivity of 0.089 ohm-centimeter after aging one week. After the same period the other two formulations had resistivities of 0.871 and 38.0 ohm-centimeters, Erratic adsorptive behavior of / sup 140/Ba was traced to in impurity in the Ba--/sup 140/La stock solution. Repurification by cation exchange did not improve the reproducibility of the separations, possibly because impurities are reint… more
Date: September 30, 1963
Creator: Eichelberger, J. F.; Grove, G. R. & Jones, L. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION C, PROGRESS REPORT ON SEPARATIONS CHEMISTRY AND SEPARATIONS PROGRESS RESEARCH FOR JANUARY-JUNE 1963

Description: Cesium Recovery from Ores. Adaptation of the phenol extraction (Phenex) process to the recovery of cesium from ore leach liquors continued to show promise. In roast-leach tests, 98 to 99% of the cesium was dissolved from pollucite ore by roasting the ore at 800 deg C with 1.8 parts of Na/sub 2/CO/sub 3/ plus 1.2 parts of NaCl and leaching with water. More than 99% of the cesium was recovered from the leach liquor and separated from other alkali metals by extracting with 4-sec-butyl-2-( alpha -m… more
Date: October 25, 1963
Creator: Brown, K.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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