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Analytical procedures for the plutonium Metal Fabrication Process

Description: A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.
Date: January 15, 1951
Creator: Kendall, L. F.
Partner: UNT Libraries Government Documents Department

PRTR second generation shim assembly

Description: From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date: November 1964
Creator: Rasmussen, D. E.
Partner: UNT Libraries Government Documents Department

Biology Seminar : methods of assaying for plutonium in biological materials

Description: From introduction: "Since plutonium is manufactured at the Hanford Works, a study of its effect on biological materials is important. To determine the amount of plutonium deposited in a biological sample, it is necessary to have an accurate method for extracting plutonium from these samples. Some of the different methods for plutonium assay are reviewed and given in this paper."
Date: November 1948
Creator: Case, A. C.
Partner: UNT Libraries Government Documents Department

Strontium Program: Quarterly Summary Report, January 1, 1960

Description: From Abstract: "This report is one of the a sequence of quarterly reports, each designed to up-date its predecessor beginning with HASL-42, "Environmental Contamination from Weapon Tests." Herein are presented data accrued since HASL-69. Plutonium-239 and cesium-137 levels in human tissue and other biological materials are also presented."
Date: January 1, 1960
Creator: Hardy, Edward P., Jr. & Klein, Stanley
Partner: UNT Libraries Government Documents Department

Alpha-n and spontaneous fission sources and spectra from individual plutonium isotopes in PuF{sub 4} and PuO{sub 2}

Description: Plutonium-containing compounds vary widely in isotopic content, and as a result, the dose as function of isotopic content also varies considerably. Determination of the dose from neutrons, decay and capture gammas from plutonium in the form of compounds thus requires that the spontaneous fission and ({alpha},n) source and spectra from each individual isotope be known. To facilitate dose calculations from plutonium-containing compounds, we have calculated the spontaneous fission and ({alpha},n) sources and spectra for 1 g of each of the plutonium isotopes in the form of either PuF{sub 4} or PuO{sub 2}. As {sup 241}Am is often a component in a mixture of plutonium isotopic compounds, the source and spectra from 1 g of {sup 241}Am mixed with PuF{sub 4} or PuO{sub 2} has also been determined. Using these results, the neutron source and spectra may be determined for any sample composition. 2 refs., 3 tabs.
Date: October 1996
Creator: Perry, R. T. & Wilson, W. B.
Partner: UNT Libraries Government Documents Department

Feasibility study of plutonium and uranium measurements in input dissolver solutions

Description: We are studying the isotope dilution gamma-ray spectrometry (IDGS) technique for the simultaneous measurements of concentrations and isotopic compositions for both plutonium and uranium in spent-fuel dissolver solutions at a reprocessing plant. Previous experiments have demonstrated that the IDGS technique can determine the elemental concentrations and isotopic compositions of plutonium in dissolver solutions. The chemical separation and recovery methods for just plutonium were ion-exchange techniques using anion exchange resin beads and filter papers. To keep both plutonium and uranium in the sample for simultaneous measurements, a new sample preparation method is being studied and developed: extraction chromatography. The technique uses U/TEVA{center_dot}Spec resin to separate fission products and recover both uranium and plutonium in the resin from dissolver solutions for measurements by high-resolution gamma-ray spectrometry.
Date: October 1, 1995
Creator: Li, T.K.; Kitagawa, O.; Kuno, Y. & Kurosawa, A.
Partner: UNT Libraries Government Documents Department

Lawrence Livermore National Laboratory Working Reference Material Production Pla

Description: This Lawrence Livermore National Laboratory (LLNL) Working Reference Material Production Plan was written for LLNL by the Los Alamos National Laboratory to address key elements of producing seven Pu-diatomaceous earth NDA Working Reference Materials (WRMS). These WRMS contain low burnup Pu ranging in mass from 0.1 grams to 68 grams. The composite Pu mass of the seven WRMS was designed to approximate the maximum TRU allowable loading of 200 grams Pu. This document serves two purposes: first, it defines all the operations required to meet the LLNL Statement of Work quality objectives, and second, it provides a record of the production and certification of the WRMS. Guidance provided in ASTM Standard Guide C1128-89 was used to ensure that this Plan addressed all the required elements for producing and certifying Working Reference Materials. The Production Plan was written to provide a general description of the processes, steps, files, quality control, and certification measures that were taken to produce the WRMS. The Plan identifies the files where detailed procedures, data, quality control, and certification documentation and forms are retained. The Production Plan is organized into three parts: a) an initial section describing the preparation and characterization of the Pu02 and diatomaceous earth materials, b) middle sections describing the loading, encapsulation, and measurement on the encapsulated WRMS, and c) final sections describing the calculations of the Pu, Am, and alpha activity for the WRMS and the uncertainties associated with these quantities.
Date: November 4, 1998
Creator: Wong, Amy; Thronas, Denise & Marshall, Robert
Partner: UNT Libraries Government Documents Department

Hydride/oxidation (HYDOX) process for conversion of plutonium metal to oxide

Description: Options for plutonium disposition require PuO<sub>2</sub> that can be used as feed material for mixed oxide (MOX) reactor fuel pellets, or glass and ceramic immobilization forms (cf. Federal Register Doc. 97-1355, Vol. 62, No. 13, January 2 1,1997). As part of a DOE-sponsored demonstration known as the Advanced Recovery and Integrated Extraction System (ARIES), conversion of plutonium to oxide by the Hydride/Oxidation (HYDOX) process will be used, along with other supporting technologies, to recover plutonium from the cores or *#34;pits" of nuclear weapons that have been determined to be surplus to national defense needs. This demonstration will be performed jointly by the Los Alamos and the Lawrence Livermore National Laboratories at the Los Alamos Plutonium Facility. The pyrochemical methods employed by HYDOX offer a simple and reliable process to recover plutonium in oxide form from various sources. This process will: Separate plutonium from other nuclear and non-nuclear materials, Convert massive metallic shapes into fine oxide particles, Produce oxide directly acceptable for MOX fuel fabrication, and Produce no solid or liquid waste. The paper describes the reactor module and operational sequences, provides up-to-date experimental results, identifies rate-controlling factors, and discusses their impact on the reactor design.
Date: June 19, 1998
Creator: Bronson, M C & Zundelevich, Y
Partner: UNT Libraries Government Documents Department

Fabrication of 12% {sup 240}Pu calorimetry standards

Description: Throughout the DOE complex, laboratories are performing calorimetric assays on items containing high burnup plutonium. These materials contain higher isotopic range and higher wattages than materials previously encountered in vault holdings. Currently, measurement control standards have been limited to utilizing 6% {sup 240}Pu standards. The lower isotopic and wattage value standards do not complement the measurement of the higher burnup material. Participants of the Calorimetry Exchange (CALEX) Program have identified the need for new calorimetric assay standards with a higher wattage and isotopic range. This paper describes the fabrication and verification measurements of the new CALEX standard containing 12% {sup 240}Pu oxide with a wattage of about 6 to 8 watts.
Date: August 1, 1995
Creator: Long, S.M.; Hildner, S.; Gutierrez, D.; Mills, C.; Garcia, W. & Gurule, C.
Partner: UNT Libraries Government Documents Department