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Mercury Removal at Idaho National Engineering and Environmental Laboratory's New Waste Calcining Facility

Description: Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas s… more
Date: March 1, 2000
Creator: Ashworth, Samuel Clay; Wood, R. A.; Taylor, D. D. & Sieme, D. D.
Partner: UNT Libraries Government Documents Department
open access

Photocatalytic Oxidation For NOx Abatement: Development of a kinetic Expression and Design Tools

Description: The ''Nitrogen Oxides Emission Reduction Program'' and ''Ozone Non-Attainment Program'' in the 1990 Clean Air Act provide guidelines for controlling NOx (NO and NO{sub 2}) emissions in new and existing stationary sources. NOx emissions have local (air quality), regional (acid rain), and global (ozone production) consequences. This study aids in developing the photocatalyst technology that has potential for use in abatement of NOx. The objective of the proposed project is to apply the principles… more
Date: September 15, 2000
Creator: Srivastava, Rajiv & Ebadian, M. A.
Partner: UNT Libraries Government Documents Department
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Test Plan for Radioactive Testing of a Vertical Direct Denitration Calciner

Description: Stored solutions containing plutonium and nitric acid and possibly uranium thorium and minor amounts of other substances will be used for development and demonstration of a vertical calciner direct denitration process for conversion of those to stable storable PuO{sub 2} rich solids. Some of those solutions are quite dilute and very impure these require either pretreatment to make them suitable for calciner feed or an alternate stabilization method. Untreated scrap solutions containing some amo… more
Date: February 3, 2000
Creator: COMPTON, J.A.
Partner: UNT Libraries Government Documents Department
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Chemical Conversion of TNT: Production of 2,4,6-Trinitrobenzoic Acid

Description: Oxidation of 2,4,6-trinitrotoluene (TNT) by aqueous nitric acid at high temperature and pressure gives 2,4,6-trinitrobenzoic acid (TNBA) and other valuable products, such as 1,3,5-trinitrobenzene (TNB). Optimization of the kinetics proved to be critical for the selective oxidation of the methyl group. High yield of a desired product can be obtained only under a narrow range of conditions. Thus, the best yield (70 to 75%) of TNBA was achieved at a 35 to 45% conversion of TNT (80% nitric acid, 19… more
Date: August 31, 2000
Creator: Astrat'ev, A.A.
Partner: UNT Libraries Government Documents Department
open access

Test Plan for Radioactive Testing of a Vertical Direct Denitration Calciner

Description: Stored solutions containing plutonium and nitric acid and possibly uranium thorium and minor amounts of other substances will be used for development and demonstration of a vertical calciner direct denitration process for conversion of those to stable storable PuO{sub 2} rich solids. Some of those solutions are quite dilute and very impure these require either pretreatment to make them suitable for calciner feed or an alternate stabilization method. Untreated scrap solutions containing some amo… more
Date: February 3, 2000
Creator: COMPTON, J.A.
Partner: UNT Libraries Government Documents Department
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Electroactive Materials for Anion Separation - Technetium from Nitrate

Description: Many contaminants of interest to the U.S. Department of Energy (DOE) exist as anions. These include the high priority pollutants chromate, pertechnetate, and nitrate ions. In addition, there are also industrial and urban applications where the separation of anionic species from aqueous streams is critical. Examples include industrial water recycle and waste water treatment (e.g., chloride ion removal for the pulp and paper industry, borate ion in the chemical and nuclear industries) and drinkin… more
Date: June 1, 2000
Creator: Sukamto, Johanes H.; Smyrl, William H.; McBreen, James; Hubler, Timothy L. & Lilga, Michael A.
Partner: UNT Libraries Government Documents Department
open access

Initiation Temperature for Runaway Tri-n-Butyl Phosphate/Nitric Acid Reaction

Description: During a review of the H-Canyon authorization basis, Defense Nuclear Facility Safety Board (DNFSB) staff members questioned the margin of safety associated with a postulated tri-n-butyl phosphate (TBP)/nitric acid runaway reaction due to the inadvertent heating of a canyon tank containing greater than 3000 lbs (1362 kg) of TBP. The margin of safety was partially based on experiments and calculations performed by the Actinide Technology Section (ATS) to support deletion of indication of tank agi… more
Date: November 28, 2000
Creator: Rudisill, T.S.
Partner: UNT Libraries Government Documents Department
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Mercury removal at Idaho National Engineering and Environmental Laboratory's New Waste Calcining Facility

Description: Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas s… more
Date: February 27, 2000
Creator: Ashworth, S. C.
Partner: UNT Libraries Government Documents Department
open access

Task Technical and Quality Assurance Plan for Testing Methods to Reduce 235 Uranium Enrichment in Tank 43H Supernatant Liquid

Description: In July of 1997, the 2H-Evaporator was shutdown due to the inability to lift material from the vessel. Inspections of the gravity drain line (GDL) showed a scale deposit coating the inside of the line. A Sample of the material was obtained and analyses performed. Plans are to chemically clean the evaporator pot by dissolving the solids in a 1.5M nitric acid solution containing depleted uranium.
Date: October 24, 2000
Creator: Hobbs, D. T.
Partner: UNT Libraries Government Documents Department
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Technical Task and Quality Assurance Plan in Support of BNFL Part B: Studies of Ion Exchange Resin Integrity under Flowsheet Extremes: Part II

Description: This task will address four items related to ion exchange stability: (1) process upset evaluation of resin in contact with 1 molar sodium permanganate at 25 and 40 degrees C, (2) accelerated aging with nitric acid solution used during normal regeneration operations, (3) prolonged contacting of SuperLig 644 resin with 5 molar nitric acid at room temperature, and (4) prolonged contacting of SuperLig 644 resin with deionized water at 60 plus/minus 5 degrees C.
Date: August 23, 2000
Creator: Nash, C.A.
Partner: UNT Libraries Government Documents Department
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Americium Separations From Nitric Acid Process Effluent Streams

Description: The aging of the US nuclear stockpile presents a number of challenges, including the ever-increasing radioactivity of plutonium residues from {sup 241}Am. Minimization of this weak gamma-emitter in process and waste solutions is desirable to reduce both worker exposure and the effects of radiolysis on the final waste product. Removal of americium from plutonium nitric acid processing effluents, however, is complicated by the presence of large.quantities of competing metals, particularly Fe and … more
Date: August 1, 2000
Creator: Barr, M. & Jarvinen, G.
Partner: UNT Libraries Government Documents Department
open access

Overview of ''Red Oil'' Frequency Analyses for F-Canyon

Description: A very small potential exists in the Savannah River Site (SRS) separations operations for an uncontrolled reaction between tri-n-butyl phosphate (TBP) and nitric acid that could result in unacceptable damage to separations facilities and a significant release of radioactive materials. The recent ''red oil'' (TBP and nitric acid) accident in Tomsk, Russia, resulted in considerable damage and radioactive release. Explosions have also occurred at SRS during the early years of operations. While the… more
Date: July 19, 2000
Creator: Lux, C.R.
Partner: UNT Libraries Government Documents Department
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Rapid Column Extraction Methods for Urine

Description: A new fecal analysis method that dissolves plutonium oxide was developed at the Westinghouse Savannah River Site. Diphonix Resin (Eichrom Industries), is used to pre-concentrate the actinides from digested fecal samples. A rapid microwave digestion technique is used to remove the actinides from the Diphonix Resin, which effectively extracts plutonium and americium from acidic solutions containing hydrofluoric acid. After resin digestion, the plutonium and americium are recovered in a small volu… more
Date: June 9, 2000
Creator: Maxwell, S. L., III
Partner: UNT Libraries Government Documents Department
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Qualification of Reillex{trademark} HPQ anion exchange resin for use in SRS processes

Description: The Phase 2 portion of the HB-Line facility was built in the early 1980's to process plutonium and neptunium from nitric acid solutions into oxide suitable for storage in a vault. Although the other portions of HB-Line were started up in the mid 1980's and have operated since that time, the anion exchange and precipitation processes in Phase 2 were never started up. As part of the material stabilization efforts, Phase 2 is currently being started up. A new anion exchange resin is needed because… more
Date: May 18, 2000
Creator: Crooks, W. J., III
Partner: UNT Libraries Government Documents Department
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