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Remediation on off-gas system deposits in a radioactive waste glass melter

Description: Since the early 1980's, research glass melters have been used at the Savannah River Laboratory (SRL) to develop the reference vitrification process for immobilization of high level radioactive waste. One of the operating concerns for these melters has been the pluggage of the off-gas system with solid deposits. Samples of these deposits were analyzed to be mixture of alkali-rich chlorides, sulfates, borates, and fluorides with entrained Fe{sub 2}O{sub 3} spinel, and frit particles. The spatial … more
Date: January 1, 1991
Creator: Jantzen, Carol M.; Choi, A. S. & Randall, C. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Feasibility of vitrifying EPICOR II organic resins

Description: Two laboratory-scale runs have recently been completed to test the feasibility of a single-step incineration/vitrification process for Three Mile Island EPICOR II resins. The process utilizes vitrification equipment, specifically a 15-cm-dia in-can melter, and a specially designed feed technique. Two process tests, each conducted with 1.2 kg of EPICOR II resins loaded with nonradioactive cesium and strontium, showed excellent operational characteristics. Less than 0.8 wt% of the resins were ent… more
Date: November 1, 1981
Creator: Buelt, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of defense-waste glass produced by full-scale vitrification equipment

Description: Three full-scale vitrification processes at the Pacific Northwest Laboratory produced over 67,000 kg of simulated nuclear-waste glass from March 1979 to August 1980. Samples were analyzed to monitor process operation and evaluate the resulting glass product. These processes are: Spray Calciner/In-Can Melter (SC/ICM); Spray Calciner/Calcine-Fed Ceramic Melter (SC/CFCM); and Liquid-Fed Ceramic Melter (LFCM). Waste components in the process feed varied less than +- 10%. The SC/ICM and SC/CFCM whic… more
Date: September 1, 1981
Creator: Lukacs, J.M.; Petkus, L.L. & Mellinger, G.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Off-gas characteristics of liquid-fed joule-heated ceramic melters

Description: The off-gas characteristics of liquid-fed joule-heated ceramic melters have been investigated as a function of melter operational condition and simulated waste feed composition. The results of these studies have established the identity and behavior patterns of gaseous emissions, the characteristics of melter-generated aerosols, the nature and magnitude of melter effluent losses and the factors affecting melter operational performance. 8 figures, 16 tables.
Date: June 1, 1982
Creator: Goles, R.W. & Sevigny, G.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Radioactive waste vitrification technology

Description: This report discusses the involvement of the Pacific Northwest Laboratory in the development of vitrification technology for the treating of radioactive, chemical and mixed wastes since the 1960's.
Date: September 1, 1992
Creator: Burkholder, H. C.; Chapman, C. C.; Ross, W. A. & Thompson, L. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of continuous liquid-fed laboratory-scale mini-melter for nuclear waste glass development

Description: A small, continuous liquid-fed mini-melter (LFMM) has been developed at Pacific Northwest Laboratory (PNL) to aid in waste glass feed slurry development. The LFMM offers several advantages over testing in large-scale melters. The LFMM requires little lead time in preparing for a test run, and the labor and material requirements are low. Real-time melting behavior of liquid feed slurries can be investigated, and feed rates can be estimated for larger-scale melters. The glass produced is represen… more
Date: February 1, 1987
Creator: Reimus, M.A.H.; Marschman, S.C. & Graff, G.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Apparatus for the dynamic and total measurement of retained fission gas

Description: This versatile apparatus provides a quick, accurate and inexpensive determination of fission gases Kr and Xe in irradiated nuclear fuels. Samples are heated to 2000/sup 0/C in a vacuum furnace under controlled temperature-time conditions and the released Kr and Xe are dynamically and integrally measured by a quadrupole mass spectrometer.
Date: January 1, 1982
Creator: Early, J.W. & Abernathey, R.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Uniformity of material in the SME and MFT

Description: The DWPF will satisfy the product consistency specification in the Waste Acceptance Preliminary Specifications through control of the chemical composition of the glass product. This control will be achieved by ensuring that each batch of feed in the Slurry Mix Evaporator (SME) will produce glass which satisfies the specification. The purpose of this report is to determine what degree of uniformity can be expected of material in the SME and Metter Feed Tank (MFT). These vessels were designed bas… more
Date: May 29, 1992
Creator: Plodinec, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Parameters influencing the aerosol capture performance of the Submerged-Bed Scrubber

Description: The Submerged-Bed Scrubber (SBS) is a novel air cleaning device that has been investigated by Pacific Northwest Laboratory (PNL) for scrubbing off gases from liquid-fed ceramic melters used to vitrify high-level waste (HLW). The concept for the SBS was originally conceived at Hanford for emergency venting of a reactor containment building. The SBS was adapted for use as a quenching scrubber at PNL because it can cool the hot melter off gas as well as remove over 90% of the airborne particles, t… more
Date: April 1, 1987
Creator: Ruecker, C.M. & Scott, P.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LFCM vitrification technology: Qualterly progress report April--June 1987

Description: This report is compiled by the Nuclear Waste treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to describe the progress in developing, testing, applying and documenting liquid-fed ceramic melter vitrification technology. Progress in the following technical subject areas during the quarter of FY 1987 is discussed: melting process chemistry and glass development; feed preparation and transfer systems, melter systems; and canister filling and handling sy… more
Date: August 1, 1988
Creator: Brouns, R. A.; Allen, C. R. & Powell, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hydrogen generation in SRAT with nitric acid and late washing flowsheets

Description: Melter feed preparation processes, incorporating a final wash of the precipitate slurry feed to Defense Waste Processing Facility (DWPF) and a partial substitution of the SRAT formic acid requirement with nitric acid, should not produce peak hydrogen generation rates during Cold Chemical Runs (CCR's) and radioactive operation greater than their current, respective hydrogen design bases of 0.024 lb/hr and 1.5 lb/hr. A single SRAT bench-scale process simulation for CCR-s produced a DWPF equivalen… more
Date: October 22, 1992
Creator: Hsu, C.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Measurement of cesium emissions during the vitrification of simulated high level radioactive waste

Description: In the Defense Waste Processing Facility at the Savannah River Site, it is desired to eliminate a startup test that would involve adding small amounts of radioactive cesium-137 to simulated high-level waste. In order to eliminate this test, a reliable method for measuring non-radioactive cesium in the offgas system from the glass melter is required. From a pilot scale melter system, offgas particulate samples were taken on filter paper media and analyzed by Inductively Coupled Plasma-Mass Spect… more
Date: January 1, 1992
Creator: Zamecnik, J. R.; Miller, D. H. & Carter, J. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Evaluation of liquid-fed ceramic melter scale-up correlations

Description: This study was conducted to determine the parameters governing factors of scale for liquid-fed ceramic melters (LFCMs) in order to design full-scale melters using smaller-scale melter data. Results of melter experiments conducted at Pacific Northwest Laboratory (PNL) and Savannah River Laboratory (SRL) are presented for two feed compositions and five different liquid-fed ceramic melters. The melter performance data including nominal feed rate and glass melt rate are correlated as a function of … more
Date: August 1, 1988
Creator: Koegler, S.S. & Mitchell, S.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LFCM (liquid-fed ceramic melter) vitrification technology: Quarterly progress report, April-June 1986

Description: This report is compiled by the Nuclear Waste Treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to document progress on liquid-fed ceramic melter (LFCM) vitrification technology. Progress in the following technical subject areas during the third quarter of FY 1986 is discussed: melting process chemistry and glass development, feed preparation and transfer systems, melter systems, canister filling and handling systems, off-gas systems, and process/produ… more
Date: February 1, 1987
Creator: Burkholder, H. C. & Allen, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Freeze and restart of the DWPF Scale Glass Melter

Description: After over two years of successful demonstration of many design and operating concepts of the DWPF Melter system, the last Scale Glass Melter campaign was initiated on 6/9/88 and consisted of two parts; (1) simulation of noble metal buildup and (2) freeze and subsequent restart of the melter under various scenarios. The objectives were to simulate a prolonged power loss to major heating elements and to examine the characteristics of transient melter operations during a startup with a limited su… more
Date: July 31, 1989
Creator: Choi, A.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LFCM (liquid-fed ceramic melter) processing characteristics of mercury

Description: An experimental-scale liquid-fed ceramic melter was used in a series of tests to evaluate the processing characteristics of mercury in simulated defense waste under various melter operating conditions. This solidification technology had no detectable capacity for incorporating mercury into its borosilicate, vitreous, product, and essentially all the mercury fed to the melter was lost to the off-gas system as gaseous effluent. An ejector venturi scrubber condensed and collected 97% of the mercur… more
Date: June 1, 1990
Creator: Goles, R.W.; Sevigny, G.J. & Andersen, C.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Control of DWPF (Defense Waste Processing Facility) melter feed composition

Description: The Defense Waste Processing Facility will be used to immobilize Savannah River Site high-level waste into a stable borosilicate glass for disposal in a geologic repository. Proper control of the melter feed composition in this facility is essential to the production of glass which meets product durability constraints dictated by repository regulations and facility processing constraints dictated by melter design. A technique has been developed which utilizes glass property models to determine … more
Date: January 1, 1990
Creator: Edwards, R. E., Jr.; Brown, K. G. & Postles, R. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Instrumentation for remote monitoring and control of liquid-fed ceramic melters

Description: New and existing instrumentation for the monitoring and control of the liquid-fed ceramic melter (LFCM) process have been tested and evaluated. The use of thermocouples for the monitoring of the glass melting process to assure a quality product and to monitor the condition of the melter equipment is well developed. Additional information about the operation of the melter including foaming, feeding, and cold cap coverage can be obtained from the temperature data. A melter viewing system consisti… more
Date: December 1, 1985
Creator: Westsik, J. H. Jr.; Wise, B. M.; Spanner, G. E. & Barnes, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Waste glass melting stages

Description: Three different simulated nuclear waste glass feeds, consisting of dried waste and glass frit, were heat treated for 1 hour in a gradient furnace at temperatures ranging from approximately 600[degrees]C--1000[degrees]C. Simulated melter feeds from the Hanford Waste Vitrification Plant (HWVP), the Defense Waste Processing Facility (DWPF), and Kernforschungszentrum Karlsruhe (KfK) in Germany were used. The samples were thin-sectioned and examined by optical microscopy to investigate the stages of… more
Date: April 1, 1993
Creator: Anderson, L. D.; Dennis, T.; Elliott, M. L. & Hrma, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Potential for steel industry energy intensity improvements: Electricity use in minimills

Description: US steel manufacturing has experienced an extended episode of creative destruction in the past twenty years. The creative destruction has been the closure of over fifty million tons worth of annual capacity in iron-ore based steel plants concurrent with the construction of nearly thirty million tons of productive capacity in scrap-based steel plants. Our focus is on the effects of the creative destruction in steel on the use of electricity in steel manufacture. This paper utilizes the plant lev… more
Date: September 1, 1992
Creator: Boyd, G.; Neifer, M.; Karlson, S. & Ross, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermal design and analysis of the HTGR fuel element vertical carbonizing and annealing furnace

Description: Computer analyses of the thermal design for the proposed HTGR fuel element vertical carbonizing and annealing furnace were performed to verify its capability and to determine the required power input and distribution. Although the furnace is designed for continuous operation, steady-state temperature distributions were obtained by assuming internal heat generation in the fuel elements to simulate their mass movement. The furnace thermal design, the analysis methods, and the results are discusse… more
Date: June 1, 1977
Creator: Llewellyn, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced radioactive waste-glass melters

Description: During pilot scale operations of the Scale Glass Melter for the US Department of Energy a team of engineers and scientists was formed to assess the need for continued melter design development to support the Defense Waste Processing Facility (DWPF), and prioritize future efforts. Recently this has taken on new importance because of selection of the DWPF Melter design as the reference for the Hanford Waste Vitrification Project (HWVP), and increased interest at the West Valley Demonstration Proj… more
Date: January 1, 1990
Creator: Bickford, D. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radioactive demonstration of DWPF product control strategy

Description: The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility (SCF) of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter and analysis of the glass product both for its composition and durability. The campaign processed approximately 10 kg (… more
Date: April 22, 1992
Creator: Andrews, M. K. & Bibler, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Application of hydration thermodynamics to control of the DWPF process

Description: The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) will incorporate the radioactivity in the 130 million liters of high-level nuclear waste at SRS in a stable borosilicate glass. Glass product specifications requite control of processing parameters to ensure glass durability. A model of glass durability, based on hydration thermodynamics, has been used at SRS to aid in formulation of waste glasses; to explain the relative durability of different glasses under identica… more
Date: January 1, 1990
Creator: Plodinec, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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