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Polyethylene solidification of low-level wastes

Description: This topical report describes the results of an investigation on the solidification of low-level radioactive waste in polyethylene. Waste streams selected for this study included those which result from advanced volume reduction technologies (dry evaporator concentrate salts and incinerator ash) and those which remain problematic for solidification using contemporary agents (ion exchange resins). Four types of commercially available low-density polyethylenes were employed which encompass a rang… more
Date: February 1, 1985
Creator: Kalb, P. D. & Colombo, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control of radioactive waste-glass melters

Description: Slurries of simulated high level radioactive waste and glass formers have been isothermally reacted and analyzed to identify the sequence of the major chemical reactions in waste vitrification, their effect on glass production rate, and the development of leach resistance. Melting rates of waste batches have been increased by the addition of reducing agents (formic acid, sucrose) and nitrates. The rate increases are attributable in part to exothermic reactions which occur at critical stages in … more
Date: January 1, 1990
Creator: Bickford, D.F. (Westinghouse Savannah River Co., Aiken, SC (USA)); Hrma, P. (Case Western Reserve Univ., Cleveland, OH (USA)) & Bowan, B.W. II (West Valley Nuclear Services Co., Inc., West Valley, NY (USA))
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Partner: UNT Libraries Government Documents Department
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Solidification of low-level radioactive wastes in masonry cement. [Masonry cement-boric acid waste forms]

Description: Portland cements are widely used as solidification agents for low-level radioactive wastes. However, it is known that boric acid wastes, as generated at pressurized water reactors (PWR's) are difficult to solidify using ordinary portland cements. Waste containing as little as 5 wt % boric acid inhibits the curing of the cement. For this purpose, the suitability of masonry cement was investigated. Masonry cement, in the US consists of 50 wt % slaked lime (CaOH/sub 2/) and 50 wt % of portland typ… more
Date: March 1, 1987
Creator: Zhou, H. & Colombo, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SCDAP/RELAP5/MOD2 code manual

Description: This report describes the materials properties correlations and computer subcodes (MATPRO) developed for use with various light water reactor (LWR) accident analysis computer programs. Formulation of the materials properties are generally semiempirical in nature. The materials properties subcodes contained in this document are for uranium, uranium dioxide, mixed uranium-plutonium dioxide fuel, zircaloy cladding, zirconium dioxide, stainless steel, stainless steel oxide, silver-indium-cadmium al… more
Date: February 1, 1990
Creator: Hohorst, J. K. (ed.) (EG and G Idaho, Inc., Idaho Falls, ID (USA))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination impacts on solidification and waste disposal

Description: Research to determine chemical and physical conditions which could lead to thermal excursions, gas generation, and/or general degradation of decontamination-reagent-loaded resins has shown that IRN-78, IONAC A-365, and IRN-77 organic ion exchange resin moisture contents vary significantly depending on the counter ion loading.'' The extent/vigor of the reaction is very highly dependent on the degree of dewatering of the resins and on the method of solution addition. The heat generation may be du… more
Date: January 1, 1988
Creator: Kempf, C.R. & Soo, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly progress report, April 1--June 30, 1977

Description: The projects reported are the following: gas reactor safety evaluation, THOR code development, SSC code development, LMFBR and LWR safety experiments, fast reactor safety code validation, technical coordination of structural integrity and fast reactor safety reliability assessment.
Date: August 1, 1977
Creator: Romano, A. J. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advances in materials science, Metals and Ceramics Division. Triannual progress report, February-May 1980

Description: Research is reported in the magnetic fusion energy and laser fusion energy programs, aluminium-air battery and vehicle research, geothermal research, nuclear waste management, basic energy science, and chemistry and materials science. (FS)
Date: August 1, 1980
Creator: Truhan, J.J. & Gordon, K.M. (eds.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation damage studies related to nuclear waste forms

Description: Much of the previously reported work on alpha radiation effects on crystalline phases of importance to nuclear waste forms has been derived from radiation effects studies of composite waste forms. In the present work, two single-phase crystalline materials, Gd/sub 2/Ti/sub 2/O/sub 7/ (pyrochlore) and CaZrTi/sub 2/O/sub 7/ (zirconolite), of relative importance to current waste forms were studied independently by doping with /sup 244/Cm at the 3 wt % level. Changes in the crystalline structure me… more
Date: December 1, 1981
Creator: Gray, W.J.; Wald, J.W. & Turcotte, R.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lysimeter study of commercial reactor waste forms: waste form acquisition characterization and full-scale leaching

Description: This report describes work conducted at Brookhaven National Laboratory (BNL) as part of a joint program with Savannah River Laboratory. Typical full-scale (55-gallon drum size) waste forms were acquired by BNL from a boiling water reactor (BWR) and a pressurized water reactor (PWR). Liquid waste stream activity concentrations were analyzed by gamma spectroscopy. This information was used to determine the waste from activity inventory, providing the necessary source term for lysimeter and leachi… more
Date: February 1, 1983
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly progress report, 1 July--30 September 1977

Description: HTGR safety evaluation included studies on fission product release; materials, chemistry, and instrumentation; structural evaluation; and analytical safety evaluation. LMFBR work included accident sequence studies, technical coordination of structural integrity, and SSC code development and validation. LWR safety studies included thermal/hydraulic analysis; THOR code development; and appraisal of analysis development in foreign countries.
Date: October 1, 1977
Creator: Kouts, H.J.C. & Kato, W.Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cesium Chloride Compatibility Testing Program. Annual report, fiscal year 1984

Description: During the course of a prior examination, it was found that one of the aged test capsules exhibited discoloration and pitting on the outer surface of the inner capsule. The damage was attributed to problems encountered in the electropolishing operation, which is used to decontaminate the inner capsule after it is loaded with the CsCl and welded shut. A study was carried out in FY 1984 to: determine if the pitting was associated with the electropolishing operation; identify acceptable solution(s… more
Date: January 1, 1985
Creator: Bryan, G. H. & Divine, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly progress report, October 1--December 31, 1977

Description: HTGR safety evaluation included studies on fission product release; materials, chemistry, and instrumentation; structural evaluation; and analytical safety evaluation. LMFBR safety evaluation included studies on accident sequences, technical coordination of structural integrity, and SSC code development and validation. LWR safety studies included thermal/hydraulic accident analysis, THOR code development, and stress corrosion cracking of PWR steam generator tubing.
Date: January 1, 1978
Creator: Romano, A.J. (comp.)
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: Highlights of the Chemical Technology (CMT) Division's activities during 1991 are presented. In this period, CMT conducted research and development in the following areas: (1) electrochemical technology, including advanced batteries and fuel cells; (2) technology for fluidized-bed combustion and coal-fired magnetohydrodynamics; (3) methods for treatment of hazardous and mixed hazardous/radioactive waste; (4) the reaction of nuclear waste glass and spent fuel under conditions expected for an uns… more
Date: March 1, 1992
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Division quarterly progress report, April 1--June 30, 1977

Description: Fuel Cycle Research and Development: Results are presented on the fluidized-bed calcination of high-level radioactive waste from reprocessing on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other projects include the development of storage technology for /sup 85/Kr waste; a study of the hydrogen mordenite catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I on silver exchanged mordenite; p… more
Date: July 1, 1977
Creator: Slansky, C. M.; Dickey, B. R.; Musgrave, B. C. & Rohde, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Division quarterly progress report, October 1--December 31, 1976

Description: The first in a series of quarterly progress reports on ERDA budgeted activities subcontracted to Allied Chemical Corporation at the Idaho National Engineering Laboratory is presented. The work is performed by the Technical Division and is divided into three subjects. Fuel cycle research and development includes fluidized-bed calcination and post treatment of commercial nuclear fuel process waste; the storage of fission product noble gas; the catalyzed reaction between NO/sub x/ and NH/sub 3/; t… more
Date: March 1, 1977
Creator: Slansky, C. M. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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