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Preliminary analysis of alternative fuel cycles for proliferation evaluation

Description: The ERDA Division of Nuclear Research and Applications proposed 67 nuclear fuel cycles for assessment as to their nonproliferation potential. The object of the assessment was to determine which fuel cycles pose inherently low risk for nuclear weapon proliferation while retaining the major benefits of nuclear energy. This report is a preliminary analysis of these fuel cycles to develop the fuel-recycle data that will complement reactor data, environmental data, and political considerations, whic… more
Date: January 1, 1977
Creator: Steindler, M. J.; Ripfel, H. C.F. & Rainey, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Considerations Affecting Deep-Well Disposal of Tritium-Bearing Low-Level Aqueous Waste from Nuclear Fuel Reprocessing Plants

Description: Present concepts of disposal of low-level aqueous wastes (LLAW) that contain much of the fission-product tritium from light water reactors involve dispersal to the atmosphere or to surface streams at fuel reprocessing plants. These concepts have been challenged in recent years. Deep-well injection of low-level aqueous wastes, an alternative to biospheric dispersal, is the subject of this presentation. Many factors must be considered in assessing its feasibility, including technology, costs, env… more
Date: March 1977
Creator: Trevorrow, L. E.; Warner, D. L. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Analysis of Factors Influencing the Reliability of Retrievable Storage Canisters for Containment of Solid High-Level Radioactive Waste

Description: The reliability of stainless steel type 304L canisters for the containment of solidified high-level radioactive wastes in the glass and calcine forms was studied. A reference system, drawn largely from information furnished by Battelle Northwest Laboratories and Atlantic Richfield Hanford Company is described. Operations include filling the canister with the appropriate waste form, interim storage at a reprocessing plant, shipment in water to a Retrievable Surface Storage Facility (RSSF), inter… more
Date: August 1976
Creator: Mecham, W. J.; Seefeldt, Waldemar B. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Technical Report 1985

Description: Highlights of the Chemical Technology (CMT) Division's activities during 1985 are presented. In this period, CMT conducted research and development in areas that include advanced batteries--mainly lithium-alloy/metal sulfide and sodium/sulfur, advanced fuel cells with molten carbonate or solid oxide electrolytes, corrosion-protective coatings for high-strength steel, coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology f… more
Date: April 1986
Creator: Steindler, M. J.; Nelson, P. A.; Ackerman, J. P. & Johnson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim Report of Brittle-Fracture Impact Studies: Development of Methodology

Description: A comprehensive methodology for characterizing the results of impact fracture of brittle waste forms is presented, and its use illustrated by application to available particle-size data obtained in impact tests of various materials. The respirable-size fraction and the total surface area of the fracture particulates are the major criteria for characterization. Particle-size distributions were all found to be characterized approximately by the two parameters of the lognormal probability function… more
Date: 1981
Creator: Mecham, W.; Jardine, L. J.; Pelto, R. H.; Reedy, G. T. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Application of Neutron-Activation Analysis to the Determination of Leach Rates of Simulated Nuclear-Waste Forms

Description: The application of neutron activation analysis to the determination of element release from simulated nuclear waste forms during leaching is described for several different glasses. Potential neutron irradiation effects are discussed, and it is shown, by a series of leach tests on activated and non-activated glass samples, that neutron irradiation has no discernible effect on the release of silicon and cesium during leaching. The radioisotopes best suited for analysis with this method and their… more
Date: February 1982
Creator: Bates, J. K.; Jardine, L. J.; Flynn, K. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alternatives for Conversion to Solid Interim Waste Forms of the Radioactive Liquid High-Level Wastes Stored at the Western New York Nuclear Service Center

Description: Techniques for isolating and solidifying the nuclear wastes in the storage tanks at the Western New York Nuclear Service Center plant have been examined. One technique involves evaporating the water and forming a molten salt containing the precipitated sludge. The salt is allowed to solidify and is stored in canisters until processing into a final waste form is to be done. Other techniques involve calcining the waste material, then agglomerating the calcine with sodium silicate to reduce its di… more
Date: August 1981
Creator: Vogler, S.; Trevorrow, L. E.; Ziegler, A. A. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of Costs for Solidification of High-Level Radioactive Waste Solutions: Glass Monoliths vs Metal Matrices

Description: A comparative economic analysis was made of four solidification processes for liquid high-level radioactive waste. Two processes produced borosilicate glass monoliths and two others produced metal matrix composites of lead and borosilicate glass beads and lead and super-calcine pellets. Within the uncertainties of the cost (1979 dollars) estimates, the cost of the four processes was about the same, with the major cost component being the cost of the primary building structure. Equipment costs a… more
Date: May 1981
Creator: Jardine, L. J.; Carlton, R. E. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Compatibility of Technologies with Regulations in the Waste Management of H-3, I-129, C-14, and Kr-85: Part 1, Initial Information Base

Description: This report summarizes the information base that was collected and reviewed in preparation for carrying out an analysis of the compatibility with regulations of waste management technologies for disposal of Hydrogen-3, Iodine-129, Carbon-14, and Krypton-85. Based on the review of this literature, summaries are presented here of waste-form characteristics, packaging, transportation, and disposal methods. Also discussed are regulations that might apply to all operations involved in disposal of th… more
Date: August 1983
Creator: Trevorrow, L. E.; Vandegrift, G. F.; Kolba, V. M. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compatibility of Technologies with Regulations in the Waste Management of H-3, I-129, C-14, and Kr-85: Part 2, Analysis

Description: Waste forms of hydrogen-3, iodine-129, carbon-14, and krypton-85 separated from fuel reprocessing streams and procedures for managing them were analyzed regarding compliance with regulations. Transportation of these wastes in certain DOT-specification packagings would be permissible, but some of these packagings may not be acceptable in some disposal situations. Transportation of gaseous krypton-85 in a currently certified cylinder is possible, but a fuel reprocessor may wish to ship larger qua… more
Date: November 1983
Creator: Trevorrow, L. E.; Kolba, V. M.; Vandegrift, G. F. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Measurement of Leaching from Simulated Nuclear-Waste Glass Using Radiotracers

Description: The use of radiotracer spiking as a method of measuring the leaching from simulated nuclear-waste glass is shown to give results comparable with other analytical detection methods. The leaching behavior of strontium-85, ruthenium-106, barium-133, cesium-137, cerium-141, europium-152, and other isotopes is measured for several defense waste glasses. These tests show that radiotracer spiking is a sensitive, multi-element technique that can provide leaching data, for actual waste elements, that ar… more
Date: September 1982
Creator: Bates, J. K.; Jardine, L. J. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Hydration Process of Nuclear-Waste Glass: An Interim Report

Description: Aging of simulated nuclear waste glass by contact with a controlled-temperature, humid atmosphere results in the formation of a double hydration layer penetrating the glass, as well as the formation of minerals on the glass surface. The hydration process can be described by Arrhenius behavior between 120 and 240 C. Results suggest that simulated aging reactions are necessary for demonstrating that nuclear waste forms can meet projected Nuclear Regulatory Commission regulations.
Date: July 1982
Creator: Bates, J. K.; Jardine, L. J. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of impact fracture of brittle solid-waste forms

Description: This paper presents a methodology for analyzing particle size distributions obtained in impact testing of brittle waste-form materials. The methodology includes (a) a linear two-parameter lognormal correlation of the weight fraction less than any given size, (b) a mathematical function of the two lognormal parameters to determine the total surface area in terms of a dimensionless shape factor, and (c) a surface-energy constant to predict the anticipated increase of surface area from the known e… more
Date: January 1, 1979
Creator: Mecham, W. J.; Jardine, L. J.; Pelto, R. H. & Steindler, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Feasibility of Underground Storage/Disposal of Noble Gas Fission Products

Description: The quantities of krypton-85 that can be released to the environment from nuclear energy production are to be limited after 1983 by Federal regulations. Although procedures for collecting the krypton-85 released in the nuclear fuel cycle have been developed to the point that they are commercially available, procedures for terminal disposal of the collected gas are still being examined for their feasibility. In this work, the possibilities of underground disposal of krypton-85 by several techniq… more
Date: August 1979
Creator: Winar, R. M.; Trevorrow, L. E. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRU decontamination of high-level Purex waste by solvent extraction using a mixed octyl(phenyl)-N,N-diisobutyl-carbamoylmethylphosphine oxide/TBP/NPH (TRUEX) solvent

Description: The TRUEX (transuranium extraction) process was tested on a simulated high-level dissolved sludge waste (DSW). A batch counter-current extraction mode was used for seven extraction and three scrub stages. One additional extraction stage and two scrub stages and all strip stages were performed by batch extraction. The TRUEX solvent consisted of 0.20 M octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide-1.4 M TBP in Conoco (C/sub 12/-C/sub 14/). The feed solution was 1.0 M in HNO/sub 3/, … more
Date: January 1, 1984
Creator: Horwitz, E. P.; Kalina, D. G.; Diamond, H.; Kaplan, L.; Vandegrift, G. F.; Leonard, R. A. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Operation with three liquid phases in a staged liquid-liquid contactor

Description: Operation with three liquid phases was demonstrated in a staged liquid-liquid contactor. The possibility that three liquid phases could be handled in a liquid-liquid contactor normally used with two liquid phases was initially established using a laboratory batch test. Tht three liquid phases were obtained using a thorium flow sheet having high concentrations of both acid and thorium. To analyze the batch test, the concept of a dimensionless dispersion number for use with two liquid phases was … more
Date: March 1, 1983
Creator: Leonard, R. A.; Ziegler, A. A.; Wigeland, R. A.; Bane, R. W. & Steindler, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characteriztion of particulate plutonium released in fuel cycle operations

Description: An estimate of the plutonium source terms is made for the fuel cycles of three reactor types on the basis of currently applied, currently available, and estimated future technology. The three reactors are LWR-U, LWR-Pu, and LMFBR. The source terms are characterized as to quantity, form, and particle size distribution. Historical operating data for existing plants and the state of the art of the technology of air cleaning are reviewed.
Date: May 1, 1976
Creator: Seefeldt, W. B.; Mecham, W. J. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Technical Report: 1991

Description: Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1991. These included electrochemical technology; fossil fuel research; hazardous waste research; nuclear waste programs; separation science and technology; integral fast reactor pyrochemical processes; actinite recovery; applied physical chemistry; basic chemistry research; analytical chemistry; research and development; and computer applications.
Date: March 1992
Creator: Argonne National Laboratory. Chemical Technology Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Management of Waste Cladding Hulls

Description: This report reviews experience and research related to the pyrophoricity of zirconium and zirconium alloys. The results of recent investigations of the behavior of Zircaloy and some observations of industrial handling and treatment of Zircaloy tubing and scrap are also discussed. A model for the management of waste Zircaloy cladding hulls from light water reactor fuel reprocessing is offered, based on an evaluation of the reviewed information. It is concluded that waste Zircaloy cladding hulls … more
Date: November 1977
Creator: Kullen, B.; Levitz, N. M. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Measurement of Leaching From Simulated Nuclear-Waste Glass Using Radiotracers

Description: The use of radiotracer spiking as a method of measuring the leaching from simulated nuclear-waste glass is shown to give results comparable with other analytical detection methods. The leaching behavior of /sup 85/Sr, /sup 106/Ru, /sup 133/Ba, /sup 137/Cs, /sup 141/Ce, /sup 152/Eu, and other isotopes is measured for several defense waste glasses. These tests show that radiotracer spiking is a sensitive, multielement technique that can provide leaching data, for actual waste elements, that are d… more
Date: September 1982
Creator: Bates, J. K.; Jardine, L. J. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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