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in creator/contributor: "Jardine, L. J."  
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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
open access

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
open access

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

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
open access

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
open access

Decision analysis of Hanford underground storage tank waste retrieval systems

Description: A decision analysis approach has been proposed for planning the retrieval of hazardous, radioactive, and mixed wastes from underground storage tanks. This paper describes the proposed approach and illustrates its application to the single-shell storage tanks (SSTs) at Hanford, Washington.
Date: May 1, 1994
Creator: Merkhofer, M. W.; Bitz, D. A.; Berry, D. L. & Jardine, L. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Secondary wastes and high explosive residues generated during production of main high explosive charges for nuclear weapons

Description: This study identifies the sources of high-explosive (HE) residues and hazardous and nonhazardous wastes generated during the production of the main HE charges for nuclear weapons, and estimates their quantities and characteristics. The results can be used as a basis for design of future handling and treatment systems for solid and liquid HE residues and wastes at any proposed new HE production facilities. This paper outlines a general methodology for documenting and estimating the volumes and c… more
Date: February 1, 1994
Creator: Jardine, L. J. & McGee, J. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Decision and systems analysis for underground storage tank waste retrieval systems and tank waste remediation system

Description: Hanford`s underground tanks (USTs) pose one of the most challenging hazardous and radioactive waste problems for the Department of Energy (DOE). Numerous schemes have been proposed for removing the waste from the USTs, but the technology options for doing this are largely unproven. To help assess the options, an Independent Review Group (IRG) was established to conduct a broad review of retrieval systems and the tank waste remediation system. The IRG consisted of the authors of this report.
Date: March 1994
Creator: Bitz, D. A.; Berry, D. L. & Jardine, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Estimate of the Sources of Plutonium-Containing Wastes Generated from MOX Fuel Production in Russia

Description: In Russia, mixed oxide (MOX) fuel is produced in a pilot facility ''Paket'' at ''MAYAK'' Production Association. The Mining-Chemical Combine (MCC) has developed plans to design and build a dedicated industrial-scale plant to produce MOX fuel and fuel assemblies (FA) for VVER-1000 water reactors and the BN-600 fast-breeder reactor, which is pending an official Russian Federation (RF) site-selection decision. The design output of the plant is based on a production capacity of 2.75 tons of weapons… more
Date: February 26, 2002
Creator: Kudinov, K. G.; Tretyakov, A. A.; Sorokin, Yu. P.; Bondin, V. V.; Manakova, L. F. & Jardine, L. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Processing of the MCC K26 Plutonium-Bearing Sludges to Recover Weapons-Grade Plutonium That is Not Under any Treaty or Monitoring Agreement

Description: Russian Federation (RF) and United States (US) collaborations from July 1998 through July 2001 conducted investigations of the Pu-bearing sludges in storage at the Mining Chemical Combine (MCC) K-26 site in order to dispose of weapons-grade plutonium and decommission the radiochemical plant. This RF work resulted in the recovery of approximately 20 kg of weapons-grade plutonium (and {approx}19 MT of uranium) from the sludges which was stored as oxide. Another method investigated and partially d… more
Date: February 26, 2002
Creator: Jardine, L. J.; Kudinov, K. G.; Tretyakov, A. A.; Bondin, V. V.; Sorokin, Y. P.; Manakova, L. F. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Estimate of the Sources of Plutonium-Containing Wastes Generated from MOX Fuel Production in Russia

Description: In Russia, mixed oxide (MOX) fuel is produced in a pilot facility ''Paket'' at ''MAYAK'' Production Association. The Mining-Chemical Combine (MCC) has developed plans to design and build a dedicated industrial-scale plant to produce MOX fuel and fuel assemblies (FA) for VVER-1000 water reactors and the BN-600 fast-breeder reactor, which is pending an official Russian Federation (RF) site-selection decision. The design output of the plant is based on production capacity of 2.75 tons of weapons p… more
Date: December 1, 2001
Creator: Kudinov, K. G.; Tretyakov, A. A.; Sorokin, Y. P.; Bondin, V. V.; Manakova, L. F. & Jardine, L. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976

Description: The Sodium Technology program currently comprises three parts. The first part is aimed at developing a model for accurately describing the behavior of tritium in LMFBRs from its formation in the core to its ultimate retention in the cold traps or release to the environment. Two important parts of this model are the behavior of the sodium cold traps and permeation of tritium through the steam-generator heat-transfer surfaces. A tritium monitor has been developed and installed on EBR-II to measur… more
Date: January 1977
Creator: McPheeters, C. C.; Jardine, L. J.; McKee, J. M.; Raue, D. J.; Renner, T. A.; Skladzien, S. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preclosure safety analysis for a prospective Yucca Mountain conceptual design repository

Description: A preliminary probabilistic risk assessment was performed for the prospective Yucca Mountain conceptual design repository. A new methodology to quantify radioactive source terms was developed and applied in the analysis. The study identified 42 event trees comprising 278 accident scenarios. The maximum offsite dose evaluated in this study is about 1000 mrem. For the majority of the accident scenarios, either the offsite dose is less than 100 mrem or the probability of occurrence is less than 1 … more
Date: December 1, 1989
Creator: Ma, C. W. & Jardine, L. J.
Item Type: Refine your search to only Article
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
open access

Decision and systems analysis for underground storage tank waste retrieval systems and tank waste remediation system

Description: Hanford`s underground storage tanks (USTs) pose one of the most challenging hazardous and radioactive waste problems for the Department of Energy (DOE). Numerous schemes have been proposed for removing the waste from the USTs, but the technology options for doing this are largely unproven. To help assess the options, an Independent Review Group (IRG) was established to conduct a broad review of retrieval systems and the tank waste remediation system. The IRG consisted of the authors of this rep… more
Date: October 1993
Creator: Berry, D. L. & Jardine, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final report of experimental laboratory-scale brittle fracture studies of glasses and ceramics

Description: An experimental program was conducted to characterize the fragments generated when brittle glasses and ceramics are impacted. The direct application of the results is to radioactive waste forms for which the effects of accidental impacts must be known or predictable. Two major measurable experimental responses used for characterization of these effects are (1) the size distribution of the fragments, including the sizes that are respirable, and (2) the increase in surface area of the brittle tes… more
Date: October 1, 1982
Creator: Jardine, L. J.; Mecham, W. J.; Reedy, G. T. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Joule-Heated Ceramic-Lined Melter to Vitrify Liquid Radioactive Wastes Containing Am241 Generated From MOX Fuel Fabrication in Russia

Description: The governments of the United Stated of America and the Russian Federation (RF) signed an Agreement September 1, 2000 to dispose of weapons plutonium that has been designated as no longer required for defense purposes. The Agreement declares that each country will disposition 34MT of excess weapons grade plutonium from their stockpiles. The preferred disposition technology is the fabrication of mixed oxide (MOx) fuel for use or burning in pressurized water reactors to destroy the plutonium. Imp… more
Date: November 16, 2004
Creator: Smith, E. C.; Bowan II, B. W.; Pegg, I. & Jardine, L. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Immobilization of AM-241, Formed Under Plutonium Metal Conversion into Monazite-Type Ceramics

Description: Lanthanum orthophosphate with the monazite structure was proposed on examinations as a suitable matrix for immobilization of future americium-containing liquid wastes, which could be formed in conversion of metallic plutonium into oxide at PA ''Mayak.'' Specimens of monazite non-active ceramics were fabricated from LaPOA powders obtained using a thin-film evaporator by either hot-pressing or cold-pressing and sintering at 900-1300 C. According to electron microprobe analysis (EMPA), scanning el… more
Date: June 6, 2001
Creator: Aloy, A. S.; Kovarskaya, E. N.; Koltsova, T. I.; Samoylov, S. E.; Rovnyi, S. I.; Medvedev, G. M. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Polymeric Species of Pu in Low Ionic Strength Media

Description: The US Government has declared that approximately 50 tons of plutonium is surplus to US needs and should be set aside for eventual disposition. The US is currently following a dual path for the disposition of this plutonium: immobilization and irradiation of mixed-oxide fuel. Some fraction of this plutonium material that is undesirable for use in mixed-oxide fuel will be immobilized in a titanate ceramic and disposed of in a geologic repository for high level waste. The reminder of Pu will be f… more
Date: January 27, 2000
Creator: Romanovski, V. V.; Palmer, C. E.; Shaw, H. F.; Bourcier, W. L. & Jardine, L. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Qualifying radioactive waste forms for geologic disposal

Description: We have developed a phased strategy that defines specific program-management activities and critical documentation for producing radioactive waste forms, from pyrochemical processing of spent nuclear fuel, that will be acceptable for geologic disposal by the US Department of Energy. The documentation of these waste forms begins with the decision to develop the pyroprocessing technology for spent fuel conditioning and ends with production of the last waste form for disposal. The need for this st… more
Date: September 1, 1994
Creator: Jardine, L. J.; Laidler, J. J. & McPheeters, C. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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