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in creator/contributor: "Trevorrow, L. E."

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Greater-confinement disposal of low-level radioactive wastes

Low-level radioactive wastes include a broad spectrum of wastes that have different radionuclide concentrations, half-lives, and physical and chemical properties. Standard shallow-land burial practice can provide adequate protection of public health and safety for most low-level wastes, but a small volume fraction (about 1%) containing most of the activity inventory (approx.90%) requires specific measures known as ''greater-confinement disposal'' (GCD). Different site characteristics and differ… more

Date: January 1, 1985

Creator: Trevorrow, L. E.; Gilbert, T. L.; Luner, C.; Merry-Libby, P. A.; Meshkov, N. K. & Yu, C.

Item Type: Article

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

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: 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

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: 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 1, Initial Information Base

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: 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

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: Report

Partner: UNT Libraries Government Documents Department

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Alternatives for Disposal of Raffinate from the TRUEX Process

Possible methods for disposing of the immobilized raffinate from TRUEX processing are reviewed. The purpose of the TRUEX process is to extract transuranium elements from high-level and TRU wastes into a small volume that can be managed at lower cost than that of the original wastes. The raffinate from the TRUEX process, containing negligible concentrations of transuranium elements, would be combined with salt solutions also derived from processing high-level waste, and the mixture would be conv… more

Date: December 1989

Creator: Trevorrow, L. E. & Vandegrift, G. F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Planning for greater confinement disposal

A report that provides guidance for planning for greater-confinement disposal (GCD) of low-level radioactive waste is being prepared. The report addresses procedures for selecting a GCD technology and provides information for implementing these procedures. The focus is on GCD; planning aspects common to GCD and shallow-land burial are covered by reference. Planning procedure topics covered include regulatory requirements, waste characterization, benefit-cost-risk assessment and pathway analysis… more

Date: January 1, 1985

Creator: Gilbert, T. L.; Luner, C.; Meshkov, N. K.; Trevorrow, L. E. & Yu, C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Feasibility of Underground Storage/Disposal of Noble Gas Fission Products

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: Report

Partner: UNT Libraries Government Documents Department

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Greater confinement disposal of radioactive wastes

Low-level radioactive waste (LLW) includes a broad spectrum of different radionuclide concentrations, half-lives, and hazards. Standard shallow-land burial practice can provide adequate protection of public health and safety for most LLW. A small volume fraction (approx. 1%) containing most of the activity inventory (approx. 90%) requires specific measures known as greater-confinement disposal (GCD). Different site characteristics and different waste characteristics - such as high radionuclide … more

Date: January 1, 1985

Creator: Trevorrow, L. E.; Gilbert, T. L.; Luner, C.; Merry-Libby, P. A.; Meshkov, N. K. & Yu, C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Planning for greater-confinement disposal

This contribution is a progress report for preparation of a document that will summarize procedures and technical information needed to plan for and implement greater-confinement disposal (GCD) of low-level radioactive waste. Selection of a site and a facility design (Phase I), and construction, operation, and extended care (Phase II) will be covered in the document. This progress report is limited to Phase I. Phase I includes determination of the need for GCD, design alternatives, and selectio… more

Date: January 1, 1984

Creator: Gilbert, T. L.; Luner, C.; Meshkov, N. K.; Trevorrow, L. E. & Yu, C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Chemical Engineering Division Fuel Cycle Programs October-December 1976

Report on fuel-cycle studies including pyrochemical separation of plutonium and americium oxides from contaminated materials of construction such as steel.

Date: 1977?

Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K. F.; Gerding, T. J.; Jardine, L. J. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tritium and noble-gas fission products in the nuclear fuel cycle. I. Reactors

No Description Available.

Date: October 1, 1974

Creator: Trevorrow, L. E.; Kullen, B. J.; Jarry, R. L. & Steindler, M. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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LABORATORY INVESTIGATIONS IN SUPPORT OF FLUID-BED FLUORIDE VOLATILITY PROCESSES. PART XIII. CONDENSED-PHASE EQUILIBRIA IN THE SYSTEM MOLYBDENUM HEXAFLUORIDE--URANIUM HEXAFLUORIDE.

No Description Available.

Date: January 1, 1966

Creator: Trevorrow, L. E.; Steindler, M. J.; Steidl, D. V. & Savage, J. T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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LABORATORY INVESTIGATIONS IN SUPPORT OF FLUID-BED FLUORIDE VOLATILITY PROCESSES. PART XII. THE MELTING-POINT DIAGRAM FOR THE SYSTEM URANIUM HEXAFLUORIDE--PLUTONIUM HEXAFLUORIDE.

No Description Available.

Date: January 1, 1966

Creator: Trevorrow, L. E.; Steindler, M. J.; Steidl, D. V. & Savage, J. T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Chemical Engineering Division waste management programs. Quarterly report, January--March 1975

Development work on the study of consolidation techniques for Zircaloy fuel-cladding hulls included scouting tests on volatility schemes for separating the zirconium as the volatile tetrachloride and ignition tests on several Zircaloy materials to further characterize the pyrophoric behavior of Zircaloy. All tests were with nonirradiated metal pending acquisition of irradiated samples. Installation is nearly complete of a glovebox facility for studies on the salvage of alpha-contaminated metals… more

Date: June 1, 1975

Creator: Steindler, M. J.; Levitz, N. M.; Mecham, W. J.; Seefeldt, W. B.; Trevorrow, L. E.; Winsch, I. O. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Chemical Engineering Division waste management programs. Quarterly report, October--December 1974

This talk about Chemical Engineering Division waste management programs. Quarterly report

Date: March 1, 1975

Creator: Steindler, M. J.; Levitz, N. M.; Mecham, W. J.; Seefeldt, W. B.; Trevorrow, L. E.; Winsch, I. O. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Argonne National Laboratory Fuel Cycle Programs Progress Report: January-March, 1978

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. This report includes fuel cycle studies in advanced solvent extraction techniques focused on development of centrifugal contactors for use in Purex processes and dispersion of liquids by explosions.

Date: April 1979

Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. J. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department