502 Matching Results

Search Results

Advanced search parameters have been applied.

Maximum total organic carbon limit for DWPF melter feed

Description: DWPF recently decided to control the potential flammability of melter off-gas by limiting the total carbon content in the melter feed and maintaining adequate conditions for combustion in the melter plenum. With this new strategy, all the LFL analyzers and associated interlocks and alarms were removed from both the primary and backup melter off-gas systems. Subsequently, D. Iverson of DWPF- T{ampersand}E requested that SRTC determine the maximum allowable total organic carbon (TOC) content in the melter feed which can be implemented as part of the Process Requirements for melter feed preparation (PR-S04). The maximum TOC limit thus determined in this study was about 24,000 ppm on an aqueous slurry basis. At the TOC levels below this, the peak concentration of combustible components in the quenched off-gas will not exceed 60 percent of the LFL during off-gas surges of magnitudes up to three times nominal, provided that the melter plenum temperature and the air purge rate to the BUFC are monitored and controlled above 650 degrees C and 220 lb/hr, respectively. Appropriate interlocks should discontinue the feeding when one or both of these conditions are not met. Both the magnitude and duration of an off-gas surge have a major impact on the maximum TOC limit, since they directly affect the melter plenum temperature and combustion. Although the data obtained during recent DWPF melter startup tests showed that the peak magnitude of a surge can be greater than three times nominal, the observed duration was considerably shorter, on the order of several seconds. The long surge duration assumed in this study has a greater impact on the plenum temperature than the peak magnitude, thus making the maximum TOC estimate conservative. Two models were used to make the necessary calculations to determine the TOC limit.
Date: March 13, 1995
Creator: Choi, A.S.
Partner: UNT Libraries Government Documents Department

Technology survey for real-time monitoring of plutonium in a vitrifier off-gas system

Description: We surveyed several promising measurement technologies for the real-time monitoring of plutonium in a vitrifier off-gas system. The vitrifier is being developed by Westinghouse Savannah River Corp. and will be used to demonstrate vitrification of plutonium dissolved in nitric acid for fissile material disposition. The risk of developing a criticality hazard in the off-gas processing equipment can be managed by using available measurement technologies. We identified several potential technologies and methods for detecting plutonium that are sensitive enough to detect the accumulation of a mass sufficient to form a criticality hazard. We recommend gross alpha-monitoring technologies as the most promising option for Westinghouse Savannah River Corp. to consider because that option appears to require the least additional development. We also recommend further consideration for several other technologies because they offer specific advantages and because gross alpha-monitoring could prove unsuitable when tested for this specific application.
Date: January 1, 1996
Creator: Berg, J.M. & Veirs, D.K.
Partner: UNT Libraries Government Documents Department

Cesium determination for the DWPF off-gas system performance test

Description: In an effort to determine the cesium decontamination factors (DF`s) of the Defense Waste Processing Facility (DWPF) melter off-gas system at the Savannah River Site, the system was verified during an off-gas performance test. The off-gas performance test occurred during the DWPF waste Qualification Campaigns, WP-16 and WP-17. The verification of the off-gas system, which eliminated the need for a startup test involving a radioactive cesium addition, was based on the analysis of nonradioactive cesium across the first and second stage High Efficiency Particulate Air (HEPA) filters. The amount of cesium on the first and second stage HEPA filters was determined by leaching samples from each HEPA filter with nitric acid and analyzing the leachate using Inductively Coupled Plasma - Mass Spectrometry (ICP-MS). The ICP-MS method has been demonstrated to be sufficiently sensitive to measure small quantities of cesium on filters. Based on the cesium results of the HEPA filter, cesium DF`s were calculated. The DF`s indicated that the DWPF HEPA filters performed better than the design basis. In addition to the HEPA filters, a determination of the cesium concentration in the melter feed, the canister glass and the off-gas condensate was made. These analyses provided information on cesium flow through the DWPF. This paper will focus on the methods used in the determination of nonradioactive cesium and the calculation of the DF`s for the DWPF melter off-gas system.
Date: April 11, 1996
Creator: Andrews, M.K.; Elder, H.H. & Boyce, W.T.
Partner: UNT Libraries Government Documents Department

Ready, set,...quit! A review of the controlled-air incinerator

Description: The Los Alamos National Laboratory (LANL) Controlled-Air Incinerator (CAI) has had a long and productive past as a research and development tool. It now appears that use of the CAI to treat LANL legacy and other wastes under the Federal Facilities Compliance Act is no longer viable due to numerous programmatic problems. This paper will review the history of the CAI. Various aspects associated with the CAI and how those aspects resulted in the loss of this Department of Energy asset as a viable waste treatment option will also be discussed. Included are past missions and tests-CAI capabilities, emissions, and permits; Federal Facility Compliance Act and associated Agreement; National Environmental Policy Act coverage; cost; budget impacts; public perception; the U.S. Environmental Protection Agency Combustion Strategy; Independent Technical Review {open_quotes}Red{close_quotes} Team review; waste treatment alternative technologies; the New Mexico Environment Department; and future options and issues.
Date: May 1, 1996
Creator: Reader, G.E.
Partner: UNT Libraries Government Documents Department

Engineering Task Plan for a vapor treatment system on Tank 241-C-103

Description: This Engineering Task Plan describes tasks and responsibilities for the design, fabrication, test, and installation of a vapor treatment system (mixing system) on Tank 241-C-103. The mixing system is to be installed downstream of the breather filter and will use a mixing blower to reduce the chemical concentrations to below allowable levels.
Date: March 9, 1995
Creator: Conrad, R.B.
Partner: UNT Libraries Government Documents Department

Development of a melter system for actinide vitrification. Revision 1

Description: The stabilization of actinides in glass was a technology considered for repository disposal of weapons-grade plutonium. Accelerated development efforts of a suitable glass composition (lanthanide borosilicate; LaBS) and melter system were completed in 1997. The other form involved in the down-selection process was a crystalline ceramic based on Synroc. As part of the glass development program, melter design activities and component testing were completed to demonstrate the feasibility of using glass as an immobilization medium. A prototypical melter was designed and built in 1997. The melter system centered on a Pt/Rh-alloy melter vessel and drain tube that were heated by two separate induction systems. An optional Pt/Rh stirrer was incorporated into the design to facilitate homogenization of the melt. Integrated powder feeding and off-gas systems completed the overall design. Concurrent with the design efforts, testing was conducted using a plutonium surrogate LaBS composition in an existing (near-scale) induction melter to demonstrate the feasibility of processing the LaBS glass on a production scale. Additionally, the drain tube configuration was successfully tested using a plutonium surrogate LaBS glass. The down-selection resulted in the selection of the ceramic option for future development. The successful testing of the induction melter system, however, showed that it is a viable technology for actinide vitrification. Currently, the melter system, complete with control and offgas components, is being successfully utilized to support the Americium/Curium vitrification program at the Savannah River Site.
Date: April 1998
Creator: Marshall, K. M.; Marra, J. C.; Coughlin, J. T.; Calloway, T. B.; Schumacher, R. F.; Zamecnik, J. R. et al.
Partner: UNT Libraries Government Documents Department

HC-21C off-gas test report

Description: Test procedure WHC-SD-CP-TC-032, HC-21C Off-Gas Test Procedure, was performed to determine the cause and establish a method of the elimination of liquid formation in the HC-21C Furnace off-gas system. This report discusses the findings of the test procedure and the changes implemented.
Date: September 12, 1995
Creator: Cunningham, L.T.
Partner: UNT Libraries Government Documents Department


Description: During this reporting period, the debinding and off-gassing furnace was switched from a vacuum furnace to a conventional kiln to solve the HIP can expansion problem during high temperature off-gassing, which caused disc distortion. Two 6.5 inch discs were produced. Both looked acceptable and one was machined. It was found that the disc hub section was little bit thin and micro cracks were seen along the disc radial directions.
Date: March 22, 2004
Creator: Huang, Xiaodi & Gertsch, Richard
Partner: UNT Libraries Government Documents Department

A bench scale study of a one-step dissolution process for treating contaminated fiberglass filters

Description: High efficiency mist eliminators (HEME) and high efficiency particulate air filters (HEPA) made of High fiberglass will be used at the Savannah River Site (SRS) to remove particulate matter from offgases generated during melter feed preparation and vitrification of high-level radioactive waste (HLW) at the Defense Waste Processing Facility (DWPF). These filters will be contaminated with high-level, radioactive species and also with various high-boiling organic compounds. For this reason, a process was developed at the Savannah River Technology Center (SRTC) that will dissolve the spent filters so that the residues may be recycled to the HLW tanks for eventual vitrification. This process involves boiling the filters sequentially in NaOH, HN0{sub 3} and NaOH, while contained in a stainless steal wire mesh frame assembly. The objective of this communication is to present some of the original preliminary work done by Ritter on the simple one-step dissolution process. The results from six bench-scale experiments are reported for the dissolution of an organically-fouled sample of HEME obtained from the Integrated DWPF Melter (IDMS) offgas filtration system. The preliminary effects of filter packing density, air sparging versus rotating basket agitation, fouling, and adding Triton X-405 as a dispersing agent are reported.
Date: December 1, 1995
Creator: Policke, T.A. & Ritter, J.A.
Partner: UNT Libraries Government Documents Department

Characterization of Off Gas Flow Surges in the DWPF Melter

Description: The Defense Waste Processing Facility (DWPF) is currently producing radioactive canisters containing vitrified high-level waste. A slurry of high-level waste and glass frit is fed into a joule-heated melter where the mixture is dried, calcined, and melted. The off gases produced are treated in an off gas system designed to remove radioactive particulate and volatile components before exhausting clean gases to the environment. Surges in the flow of off gas can occur by various means, and must be accommodated by the melter off gas system. A method for calculating the magnitude of off gas surges is presented and applied to actual plant data. The melter off gas control system is shown to mitigate the effects of most flow surges without significant impact to plant operations.
Date: March 15, 1999
Creator: Calloway, T.B. Jr.
Partner: UNT Libraries Government Documents Department

In situ gas treatment technology demonstration test plan

Description: This document defines the objectives and requirements associated with undertaking a field demonstration of an in situ gas treatment appoach to remediation chromate-contaminated soil. The major tasks presented in this plan include the design and development of the surface gas treatment system, performance of permitting activities, and completion of site preparation and field testing activities.
Date: February 16, 1996
Creator: Thornton, E.C. & Miller, R.D.
Partner: UNT Libraries Government Documents Department

Preoperational test report, primary ventilation condenser cooling system

Description: This represents the preoperational test report for the Primary Ventilation Condenser Cooling System, Project W-030. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. The system uses a closed chilled water piping loop to provide offgas effluent cooling for tanks AY101, AY102, AZ1O1, AZ102; the offgas is cooled from a nominal 100 F to 40 F. Resulting condensation removes tritiated vapor from the exhaust stack stream. The piping system includes a package outdoor air-cooled water chiller with parallel redundant circulating pumps; the condenser coil is located inside a shielded ventilation equipment cell. The tests verify correct system operation and correct indications displayed by the central Monitor and Control System.
Date: October 29, 1997
Creator: Clifton, F.T.
Partner: UNT Libraries Government Documents Department

Maximum organic carbon limits at different melter feed rates (U)

Description: This report documents the results of a study to assess the impact of varying melter feed rates on the maximum total organic carbon (TOC) limits allowable in the DWPF melter feed. Topics discussed include: carbon content; feed rate; feed composition; melter vapor space temperature; combustion and dilution air; off-gas surges; earlier work on maximum TOC; overview of models; and the results of the work completed.
Date: December 1995
Creator: Choi, A. S.
Partner: UNT Libraries Government Documents Department

Selective olefin recovery

Description: This report presents the results of the outstanding studies on olefin product purities, pyridine recovery, and absorber offgas utilization. Other reports issued since the May 2 technical review meeting in Grangemouth evaluated the impact of the new VLE data on the solution stripping operation and the olefin loadings in the lean and rich solutions. This report completes the bulk of Stone & Webster`s engineering development of the absorber/stripper process for Phase I. The final feasibility study report (to be issued in August) will present an updated design and economics.
Date: July 1, 1996
Partner: UNT Libraries Government Documents Department

Maximum total organic carbon limits at different DWPF melter feed maters (U)

Description: The document presents information on the maximum total organic carbon (TOC) limits that are allowable in the DWPF melter feed without forming a potentially flammable vapor in the off-gas system were determined at feed rates varying from 0.7 to 1.5 GPM. At the maximum TOC levels predicted, the peak concentration of combustible gases in the quenched off-gas will not exceed 60 percent of the lower flammable limit during a 3X off-gas surge, provided that the indicated melter vapor space temperature and the total air supply to the melter are maintained. All the necessary calculations for this study were made using the 4-stage cold cap model and the melter off-gas dynamics model. A high-degree of conservatism was included in the calculational bases and assumptions. As a result, the proposed correlations are believed to by conservative enough to be used for the melter off-gas flammability control purposes.
Date: January 1, 1996
Creator: Choi, A.S.
Partner: UNT Libraries Government Documents Department

Hanford High-Level Waste Vitrification Program at the Pacific Northwest National Laboratory: technology development - annotated bibliography

Description: This report provides a collection of annotated bibliographies for documents prepared under the Hanford High-Level Waste Vitrification (Plant) Program. The bibliographies are for documents from Fiscal Year 1983 through Fiscal Year 1995, and include work conducted at or under the direction of the Pacific Northwest National Laboratory. The bibliographies included focus on the technology developed over the specified time period for vitrifying Hanford pretreated high-level waste. The following subject areas are included: General Documentation; Program Documentation; High-Level Waste Characterization; Glass Formulation and Characterization; Feed Preparation; Radioactive Feed Preparation and Glass Properties Testing; Full-Scale Feed Preparation Testing; Equipment Materials Testing; Melter Performance Assessment and Evaluations; Liquid-Fed Ceramic Melter; Cold Crucible Melter; Stirred Melter; High-Temperature Melter; Melter Off-Gas Treatment; Vitrification Waste Treatment; Process, Product Control and Modeling; Analytical; and Canister Closure, Decontamination, and Handling
Date: September 1, 1996
Creator: Larson, D.E.
Partner: UNT Libraries Government Documents Department

Technical bases for the use of CIF{sub 3} in the MSRE reactive gas removal project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: Nearly impermeable, non-volatile deposits in the Molten Salt Reactor Experiment (MSRE) off-gas piping are impeding the removal of reactive gases from that system. The deposits almost certainly consist of reduced uranium fluorides or of uranium oxyfluorides. Treatment with ClF{sub 3} is a non-intrusive method capable of chemically converting these compounds back to UF{sub 6}, which can then be removed as a gas. This report discusses the technical bases for the use of ClF{sub 3} treatments in this system. A variety of issues are examined, and where the necessary information exists or has been developed, the resolution discussed. The more important of these issues include the efficacy of ClF{sub 3} at deposit removal under the conditions imposed by the MSRE system, materials compatibility of ClF{sub 3} and its reaction products, and operational differences in the Reactive Gas Removal System imposed by the presence of ClF{sub 3} and its products.
Date: June 1997
Creator: Trowbridge, L. D.
Partner: UNT Libraries Government Documents Department

Minimum TI4085D interlock setpoint at 1.0 GPM sludge-only feed rate and 14,000 ppm TOC

Description: DWPF-Engineering requested that SRTC determine the minimum indicated melter vapor space temperature that must be maintained in order to minimize the potential for off-gas flammability during a steady sludge-only feeding operation at 1.0 GPM containing 14,000 ppm total organic carbon. The detailed scope of this request is described in the technical task request, HLW-DWPF-TTR-960092 (DWPT Activity No. DWPT-96-0065). In response to this request, a dynamic simulation study was conducted in which the concentration of flammable gases was tracked throughout the course of a simulated 3X off-gas surge using the melter off-gas (MOG) dynamics model. The results of simulation showed that as long as the melter vapor space temperature as indicated on TI4085D is kept at 570 degrees C or higher, the peak concentration of combustible gases in the melter off-gas system is not likely to exceed 60 percent of the lower flammability limit (LFL). The minimum TI4085D of 570 degrees C is valid only when the air purges to FIC3221A and FIC3221B are maintained at or above 850 and 250 lb/hr, respectively. All the key bases and assumptions along with the input data used in the simulation are described in the attached E-7 calculation note.
Date: November 5, 1996
Creator: Choi, A.S.
Partner: UNT Libraries Government Documents Department

Initial field test of High-Energy Corona process for treating a contaminated soil-offgas stream

Description: The High-Energy Corona (HEC) technology for treating process offgases has been under development at Pacific Northwest Laboratory (PNL) since 1991. The HEC process uses high-voltage electrical discharges in air to ionize the air, forming a low-temperature plasma that would be expected to destroy a wide variety of organic compounds in air. The plasma contains strong oxidants, possibly including hydroxyl radicals, hydroperoxy radicals, superoxide radicals, various excited as well as ionized forms of oxygen, high-energy electrons, and ultraviolet (UV) light. Because the high-voltage plasma is produced near ambient temperatures and pressures, yet exhibits extremely rapid destruction kinetics with relatively low power requirements, the HEC technique appears promising as a low-cost treatment technique (Virden et al. 1992). As part of the Volatile Organic Compound (VOC) Nonarid Integrated Demonstration (ID) at the DOE Savannah River Site, research activities were initiated in December 1991 to develop a prototype HEC process for a small-scale field demonstration to treat a soil-offgas stream contaminated with trichloroethylene (TCE) and perchloroethylene (PCE) at varying concentrations. Over an 18-month period, the HEC technology was developed on a fast track, through bench and pilot scales into a trailer-mounted system that was tested at the Nonarid ID. Other national laboratories, universities, and private companies have also participated at the Nonarid ID to demonstrate a number of conventional, emerging and innovative approaches for treating the same soil-offgas stream.
Date: April 1, 1995
Creator: Shah, R R; Garcia, R E; Jeffs, J T; Virden, J W & Heath, W O
Partner: UNT Libraries Government Documents Department

Mercury emissions control technologies for mixed waste thermal treatment

Description: EPA has identified wet scrubbing at low mercury feedrates, as well as carbon adsorption via carbon injection into the offgas or via flow through fixed carbon beds, as control technologies that can be used to meet the proposed Maximum Achievable Control Technology (MACT) rule limit for mercury emissions from hazardous waste incinerators. DOE is currently funding demonstrations of gold amalgamation that may also control mercury to the desired levels. Performance data from a variety of sources was reviewed to determine ranges of achievable mercury control. Preliminary costs were estimated for using these technologies to control mercury emissions from mixed waste incineration. Mercury emissions control for mixed waste incineration may need to be more efficient than for incineration of other hazardous wastes because of higher mercury concentrations in some mixed waste streams. However, mercury control performance data for wet scrubbing and carbon adsorption is highly variable. More information is needed to demonstrate control efficiencies that are achievable under various design and operating conditions for wet scrubbing, carbon adsorption, and gold amalgamation technologies. Given certain assumptions made in this study, capital costs, operating costs, and lifecycle costs for carbon injection, carbon beds, and gold amalgamation generally vary for different assumed mercury feedrates and for different offgas flowrates. Assuming that these technologies can in fact provide the necessary mercury control performance, each of these technologies may be less costly than the others for certain mercury feedrates and the offgas flowrates.
Date: December 31, 1997
Creator: Chambers, A.; Knecht, M.; Soelberg, N.; Eaton, D.; Roberts, D. & Broderick, T.
Partner: UNT Libraries Government Documents Department

Sodium carbonate facility at Argonne National Laboratory - West

Description: The Sodium Carbonate Facility, located at Argonne National Laboratory - West (ANL-W) in Idaho, was designed and built as an addition to the existing Sodium Processing Facility. The Sodium Process and Sodium Carbonate Facilities will convert radioactive sodium into a product that is acceptable for land disposal in Idaho. The first part of the process occurs in the Sodium Process Facility where radioactive sodium is converted into sodium hydroxide (caustic). The second part of the process occurs in the Sodium Carbonate Facility where the caustic solution produced in the Sodium Process Facility is converted into a dry sodium carbonate waste suitable for land disposal. Due to the radioactivity in the sodium, shielding, containment, and HEPA filtered off-gas systems are required throughout both processes.
Date: September 1, 1997
Creator: McDermott, M.D.; Henslee, S.P.; Michelbacher, J.A.; Rosenberg, K.E. & Wells, P.B.
Partner: UNT Libraries Government Documents Department

Removal of uranium and salt from the Molten Salt Reactor Experiment

Description: In 1994, migration of {sup 233}U was discovered to have occurred at the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory (ORNL). This paper describes the actions now underway to remove uranium from the off-gas piping and the charcoal bed, to remove and stabilize the salts, and to convert the uranium to a stable oxide for long-term storage.
Date: June 1, 1998
Creator: Peretz, F.J.; Rushton, J.E.; Faulkner, R.L.; Walker, K.L. & Del Cul, G.D.
Partner: UNT Libraries Government Documents Department