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High Efficiency Particulate Air (HEPA) Filter Generation, Characterization, and Disposal Experiences at the Oak Ridge National Laboratory

Description: High Efficiency Particulate Air filtration is an essential component of the containment and ventilation systems supporting the research and development activities at the Oak Ridge National Laboratory. High Efficiency Particulate Air filters range in size from 7.6cm (3 inch) by 10.2 cm (4 inch) cylindrical shape filters to filter array assemblies up to 2.1 m (7 feet) high by 1.5 m (5 feet) wide. Spent filters are grouped by contaminates trapped in the filter media and become one of the components in the respective waste stream. Waste minimization and pollution prevention efforts are applied for both radiological and non-radiological applications. Radiological applications include laboratory hoods, glove boxes, and hot cells. High Efficiency Particulate Air filters also are generated from intake or pre-filtering applications, decontamination activities, and asbestos abatement applications. The disposal avenues include sanitary/industrial waste, Resource Conservation and Recovery Act and Toxic Substance Control Act, regulated waste, solid low-level waste, contact handled transuranic, and remote handled transuranic waste. This paper discusses characterization and operational experiences associated with the disposal of the spent filters across multiple applications.
Date: February 28, 2002
Creator: Coffey, D. E.
Partner: UNT Libraries Government Documents Department

Planning for the Management and Disposition of Newly Generated TRU Waste from REDC

Description: This paper describes the waste characteristics of newly generated transuranic waste from the Radiochemical Engineering and Development Center at the Oak Ridge National Laboratory and the basic certification structure that will be proposed by the University of Tennessee-Battelle and Bechtel Jacobs Company LLC to the Waste Isolation Pilot Plant for this waste stream. The characterization approach uses information derived from the active production operations as acceptable knowledge for the Radiochemical Engineering and Development Center transuranic waste. The characterization approach includes smear data taken from processing and waste staging hot cells, as well as analytical data on product and liquid waste streams going to liquid waste disposal. Bechtel Jacobs Company and University of Tennessee-Battelle are currently developing the elements of a Waste Isolation Pilot Plant-compliant program with a plan to be certified by the Waste Isolation Pilot Plant for shipment of newly generated transuranic waste in the next few years. The current activities include developing interface plans, program documents, and waste stream specific procedures.
Date: February 26, 2002
Creator: Coffey, D. E.; Forrester, T. W. & Krause, T.
Partner: UNT Libraries Government Documents Department

Waste Examination Assay Facility operations: TRU waste certification

Description: The ORNL Waste Examination Assay Facility (WEAF) was established to nondestructively assay (NDA) transuranic (TRU) waste generated at Oak Ridge National Laboratory (ORNL). The present facility charter encompasses the NDA and nondestructive examination (NDE) of both TRU and low-level wastes (LLW). Presently, equipment includes a Neutron Assay System (NAS), a Segmented Gamma Scanner (SGS), a drum-sized Real-Time Radiography (RTR) system, and a Neutron Slab Detector (NSD). The first three instruments are computer interfaced. Approximately 2300 TRU waste drums have been assayed with the NAS and the SGS. Another 3000 TRU and LLW drums have been examined with the RTR unit. Computer data bases have been developed to collate the large amount of data generated during the assays and examinations. 6 refs., 1 tab.
Date: January 1, 1987
Creator: Schultz, F.J.; Caylor, B.A.; Coffey, D.E. & Phoenix, L.B.
Partner: UNT Libraries Government Documents Department

Neutron and gamma-ray nondestructive examination of contact-handled transuranic waste at the ORNL TRU Waste Drum Assay Facility

Description: A nondestructive assay system, which includes the Neutron Assay System (NAS) and the Segmented Gamma Scanner (SGS), for the quantification of contact-handled (<200 mrem/h total radiation dose rate at contact with container) transuranic elements (CH-TRU) in bulk solid waste contained in 208-L and 114-L drums has been in operation at the Oak Ridge National Laboratory since April 1982. The NAS has been developed and demonstrated by Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) for use by most US Department of Energy Defense Plant (DOE-DP) sites. More research and development is required, however, before the NAS can provide complete assay results for other than routine defense waste. To date, 525 ORNL waste drums have been assayed, with varying degrees of success. The isotopic complexity of the ORNL waste creates a correspondingly complex assay problem. The NAS and SGS assay data are presented and discussed. Neutron matrix effects, the destructive examination facility, and enriched uranium fuel-element assays are also discussed.
Date: March 1, 1985
Creator: Schultz, F.J.; Coffey, D.E.; Norris, L.B. & Haff, K.W.
Partner: UNT Libraries Government Documents Department

First-year evaluation of a nondestructive assay system for the examination of ORNL TRU waste

Description: The Oak Ridge National Laboratory has been selected as the demonstration site for a new transuranic neutron assay system (NAS) developed at the Los Alamos National Laboratory. In addition, in order to meet specific ORNL program objectives, an upgraded segmented gamma-ray drum scanner has been integrated into the nondestructive assay (NDA) system to serve as a radioisotope identifier and as a quantitative assay backup to the NAS. A verification study, wherein selected waste drums will be emptied into glove boxes and their contents sampled and subsequently gamma-ray assayed, will take place in FY 1984. Results will be compared to those obtained from the NDA techniques. The NAS uses pulsed-neutron interrogation (differential- dieaway technique) and passive neutron measurements to determine fissile component and an upper-limit estimate of the total TRU activity contained in each waste drum. Of the 171 waste drums assayed to date, nine drums were determined to contain less than 10 nCi/g TRU isotopes. An additional number of drums (approximately 20%) are expected to be categorized as non-TRU, which is presently defined as less than 100 nCi/g TRU concentration. This requires a detailed analysis of the data which includes waste matrix compensation, systematic qualitative and quantitative gamma-ray analyses, and interpretation of neutron multiplicity data. Reproducibility of the active assay measurements on a single waste drum indicate agreement to +-3% relative error. 14 references, 24 figures, 8 tables.
Date: April 1, 1984
Creator: Schultz, F.J.; Haff, K.W.; Coffey, D.E.; Norris, L.B.; Caldwell, J.T.; Close, D.A. et al.
Partner: UNT Libraries Government Documents Department

Application of nondestructive assay technology in Oak Ridge National Laboratory's waste management program

Description: Waste characterization is the process whereby physical properties and chemical composition of waste are determined. Waste characterization is an important element of a waste certification program in that it provides information which is necessary to certify that waste meets the acceptance criteria for storage, treatment, or disposal. Department of Energy (DOE) Order 5820.2A and WIPP-DOE-069 list and describe the germane waste form, package, and container criteria for the storage of both solid low-level waste (SLLW) and transuranic (TRU) waste, including chemical composition and compatibility, hazardous material content, fissile material content, equivalent alpha activity, thermal heat output, and absence of free liquids, explosives, and compressed gases. At the Oak Ridge National Laboratory (ORNL), the responsibility for waste characterization begins with the individual(s) who generate the waste. The generator must be able to document the type and estimate the quantity of various materials which have been placed into the waste container. Analyses of process flow sheets and a statistically valid sampling program can provide much of the required information as well as a documented level of confidence in the acquired data. A program is being instituted in which the major generator facilities perform radionuclide assay of small packets of waste prior to being placed into a waste drum. 10 refs., 1 fig., 1 tab.
Date: January 1, 1990
Creator: Schultz, F.J.; Smith, M.A.; Brandenburg, R.W.; Caylor, B.A.; Coffey, D.E.; Hensley, D.C. et al.
Partner: UNT Libraries Government Documents Department