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Glass Development for Treatment of LANL Evaporator Bottoms Waste

Description: Vitrification is an attractive treatment option for meeting the stabilization and final disposal requirements of many plutonium (Pu) bearing materials and wastes at the Los Alamos National Laboratory (LANL) TA-55 facility, Rocky Flats Environmental Technology Site (RFETS), Hanford, and other Department of Energy (DOE) sites. The Environmental Protection Agency (EPA) has declared that vitrification is the "best demonstrated available technology" for high- level radioactive wastes (HLW) (Federal … more
Date: November 20, 1998
Creator: Smith, Donald E.; Piepel, Gregory F.; Veazey, Gerald W.; Vienna, John D.; Elliott, Michael L.; Nakaoka, Ronald K. et al.
Partner: UNT Libraries Government Documents Department
open access

Liquidus Temperature Data for DWPF Glass

Description: A liquidus temperature (T{sub L}) database has been developed at the Pacific Northwest Laboratory (PNNL) for the Defense Waste Processing Facility (DWPF) glass composition region to support DWPF process control schemes. A test matrix consisting of 53 glasses (including two duplicates) was generated at the Savannah River Technology Center (SRTC) using statistical experimental design methods. To ensure homogeneity, glasses were melted twice. Both melts were performed at T = T{sub 5} + {Delta}T, w… more
Date: December 1, 1998
Creator: Hrma, Pavel R.; Vienna, John D.; Mika, Martin; Crum, Jarrod V. & Piepel, Gregory F.
Partner: UNT Libraries Government Documents Department
open access

Hanford Immobilized LAW Product Acceptance: Initial Tanks Focus Area Testing Data Package

Description: A matrix of 55 glasses was developed and tested with the aim to identify the impact of glass composition on the long-term corrosion behavior and to develop an acceptable low-activity waste glass composition region. Of the 55 glasses, 45 were designed to systematically vary the glass composition and 10 were selected because large and growing databases on their corrosion characteristics had accumulated. The performance of these 55 glasses in the vapor-phase hydration test (VHT) and product consis… more
Date: February 8, 2000
Creator: Vienna, John D.; Jiricka, Antonin; McGrail, B. Peter; Jorgensen, Benaiah M.; Smith, Donald E.; Allen, Benjamin R. et al.
Partner: UNT Libraries Government Documents Department
open access

Preparation and Characterization of {sup 238}Pu-Ceramics for Radiation Damage Experiments

Description: The results from this initial characterization of the {sup 238}Pu- and {sup 239}Pu-bearing ceramics showed that the target phase assemblage was achieved in all but one material, {sup 238}Pu-zirconolite baseline. This {sup 238}Pu-zirconolite baseline material appears to have been prepared incorrectly with a 14 mass% excess of Pu (9.6 mass% actual vs. 8.4 mass% target; 4.8 mole% actual vs. 4.1 mole% target). It is not surprising that PuO{sub 2} was found to be one of the dominant phases. The dens… more
Date: June 15, 2000
Creator: Strachan, Denis M.; Scheele, Randall D.; Buchmiller, William C.; Vienna, John D.; Sell, Richard L. & Elovich, Robert J.
Partner: UNT Libraries Government Documents Department
open access

Formulation Efforts for Direct Vitrification of INEEL Blend Calcine Waste Simulate: Fiscal Year 2000

Description: This report documents the results of glass formulation efforts for Idaho National Engineering and Environmental Laboratory (INEEL) high level waste (HWL) calcine. Two waste compositions were used during testing. Testing started by using the Run 78 calcine composition and switched to simulated Blend calcine composition when it became available. The goal of the glass formulation efforts was to develop a frit composition that will accept higher waste loading that satisfies the glass processing and… more
Date: March 30, 2001
Creator: Crum, Jarrod V.; Vienna, John D.; Peeler, David K. & Reamer, I. A.
Partner: UNT Libraries Government Documents Department
open access

Formulation Efforts for Direct Vitrification of INEEL Blend Calcine Waste Simulate: Fiscal Year 2000

Description: The TFA uses a systematic process for developing its annual program that draws from the tanks science and technology development needs expressed by the five DOE tank waste sites. TFA's annual program development process is iterative and involves the following steps: Collection of site needs; Needs analysis; Development of technical responses and initial prioritization; Refinement of the program for the next fiscal year; Formulation of the Corporate Review Budget (CRB); Preparation of Program Ex… more
Date: March 30, 2001
Creator: Crum, Jarrod V; Vienna, John D & Peeler, David K
Partner: UNT Libraries Government Documents Department
open access

High-Level Waste Melter Study Report

Description: At the Hanford Site in Richland, Washington, the path to site cleanup involves vitrification of the majority of the wastes that currently reside in large underground tanks. A Joule-heated glass melter is the equipment of choice for vitrifying the high-level fraction of these wastes. Even though this technology has general national and international acceptance, opportunities may exist to improve or change the technology to reduce the enormous cost of accomplishing the mission of site cleanup. Co… more
Date: July 13, 2001
Creator: Perez, Joseph M.; Bickford, Dennis F.; Day, Delbert E.; Kim, Dong-Sang; Lambert, Steven L.; Marra, Sharon L. et al.
Partner: UNT Libraries Government Documents Department
open access

High-Level Waste Melter Study Report

Description: At the Hanford Site in Richland, Washington, the path to site cleanup involves vitrification of the majority of the wastes that currently reside in large underground tanks. A Joule-heated glass melter is the equipment of choice for vitrifying the high-level fraction of these wastes. Even though this technology has general national and international acceptance, opportunities may exist to improve or change the technology to reduce the enormous cost of accomplishing the mission of site cleanup. Co… more
Date: July 13, 2001
Creator: Perez, Joseph M., Jr.; Bickford, Dennis F.; Day, Delbert E.; Kim, Dong-Sang; Lambert, Steven L.; Marra, Sharon L. et al.
Partner: UNT Libraries Government Documents Department
open access

Database and Interim Glass Property Models for Hanford HLW Glasses

Description: The purpose of this report is to provide a methodology for an increase in the efficiency and a decrease in the cost of vitrifying high-level waste (HLW) by optimizing HLW glass formulation. This methodology consists in collecting and generating a database of glass properties that determine HLW glass processability and acceptability and relating these properties to glass composition. The report explains how the property-composition models are developed, fitted to data, used for glass formulation… more
Date: July 24, 2001
Creator: Hrma, Pavel R.; Piepel, Gregory F.; Vienna, John D.; Cooley, Scott K.; Kim, Dong-Sang & Russell, Renee L.
Partner: UNT Libraries Government Documents Department
open access

Database and Interim Glass Property Models for Hanford HLW Glasses

Description: The purpose of this report is to provide a methodology for an increase in the efficiency and a decrease in the cost of vitrifying high-level waste (HLW) by optimizing HLW glass formulation. This methodology consists in collecting and generating a database of glass properties that determine HLW glass processability and acceptability and relating these properties to glass composition. The report explains how the property-composition models are developed, fitted to data, used for glass formulation… more
Date: July 24, 2001
Creator: Hrma, Pavel R; Piepel, Gregory F; Vienna, John D; Cooley, Scott K; Kim, Dong-Sang & Russell, Renee L
Partner: UNT Libraries Government Documents Department
open access

Sulfur Partitioning During Vitrification of INEEL Sodium Bearing Waste: Status Report

Description: The sodium bearing tank waste (SBW) at Idaho National Engineering and Environmental Laboratory (INEEL) contains high concentrations of sulfur (roughly 5 mass% of SO3 on a nonvolatile oxide basis). The amount of sulfur that can be feed to the melter will ultimately determine the loading of SBW in glass produced by the baseline (low-temperature, joule-heated, liquid-fed, ceramic-lined) melter. The amount of sulfur which can be fed to the melter is determined by several major factors including: th… more
Date: July 31, 2001
Creator: Darab, John G.; Graham, Dennis D.; Macisaac, Brett D.; Russell, Renee L.; Smith, Harry D.; Vienna, John D. et al.
Partner: UNT Libraries Government Documents Department
open access

Sulfur Partitioning During Vitrification of INEEL Sodium Bearing Waste: Status Report

Description: The sodium bearing tank waste (SBW) at Idaho National Engineering and Environmental Laboratory (INEEL) contains high concentrations of sulfur (roughly 5 mass% of SO3 on a nonvolatile oxide basis). The amount of sulfur that can be feed to the melter will ultimately determine the loading of SBW in glass produced by the baseline (low-temperature, joule-heated, liquid-fed, ceramic-lined) melter. The amount of sulfur which can be fed to the melter is determined by several major factors including: th… more
Date: July 31, 2001
Creator: Darab, John G.; Macisaac, Brett D.; Russell, Renee L.; Smith, Harry D. & Vienna, John D.
Partner: UNT Libraries Government Documents Department
open access

Hanford Immobilized LAW Product Acceptance Testing: Tanks Focus Area Results

Description: Immobilizing low-activity waste (LAW) stored at Hanford site will result in approximately 200 000 m3 of waste glass. It must be demonstrated that this glass can adequately retain radionuclides and prevent contamination of the surrounding environment. A study is being performed to determine the effect of glass composition on its capability to withstand the conditions in the Hanford site burial scenario. To predict the long-term corrosion behavior of waste glass, it is necessary to study the comp… more
Date: December 31, 2001
Creator: Vienna, John D.; Hrma, Pavel R.; Jiricka, Antonin; Smith, Donald E.; Lorier, Troy H.; Reamer, Irene A. et al.
Partner: UNT Libraries Government Documents Department
open access

Glass Formulation Development for INEEL Sodium-Bearing Waste

Description: Studies were performed to develop and test a glass formulation for immobilization of sodium-bearing waste (SBW). SBW is a high soda, acid high activity waste stored at the INEEL in 10 underground tanks. It was determined in previous studies that SBW?s sulfur content dictates the its loading in borosilicate glasses to be melted by currently assumed processes. If the sulfur content (which is ~4.5 mass% SO3 on a non-volatile oxide basis in SBW) of the melter feed is too high then a molten alkali s… more
Date: August 1, 2002
Creator: Vienna, John D.; Buchmiller, William C.; Crum, Jarrod V.; Graham, Dennis D.; Kim, Dong-Sang; Macisaac, Brett D. et al.
Partner: UNT Libraries Government Documents Department
open access

Hanford Immobilized LAW Product Acceptance: Tanks Focus Area Testing Data Package II

Description: This report is a continuation of the Hanford Immobilized Low Activity Waste (LAW) Product Acceptance (HLP): Initial Tanks Focus Area Testing Data Package (Vienna et al. 2000). In addition to new 5000-h product consistency test (PCT), vapor hydration test (VHT), and alteration products data, some previously reported data together with relevant background information are included for an easily accessible source of reference when comparing the response of the various glasses to different test cond… more
Date: August 8, 2002
Creator: Schulz, Rebecca L.; Lorier, Troy H.; Peeler, David K.; Brown, Kevin G.; Reamer, Irene A.; Vienna, John D. et al.
Partner: UNT Libraries Government Documents Department
open access

Model for TCLP Releases from Waste Glasses

Description: A first-order property model for normalized Toxicity Characteristic Leaching Procedure (TCLP) release as a function of glass composition was developed using collected data from various studies. The normalized boron release is used to estimate the release of toxic elements based on the observation that the boron release represents the conservative release for those constituents of interest. The current TCLP model has two targeted application areas: (1) delisting of waste-glass product as radioac… more
Date: September 1, 2002
Creator: Kim, Dong-Sang & Vienna, John D.
Partner: UNT Libraries Government Documents Department
open access

Selective Leaching of Chromium from Hanford Tank Sludge 241-U-108

Description: This study evaluated the oxidants permanganate, MnO4-, and peroxynitrite, ONOO-, as selective chromium-leaching agents from washed 241-U-108 tank sludge under varying conditions of hydroxide concentration, temperature, and time. The mass changes and final sludge compositions were evaluated using glass-property models to ascertain the relative impacts of the various oxidative alkaline leach conditions on the amount of borosilicate glass required to immobilize a given amount of washed 241-U-108 H… more
Date: September 9, 2002
Creator: Rapko, Brian M. & Vienna, John D.
Partner: UNT Libraries Government Documents Department
open access

Alkaline Leaching of Key, Non-Radioactive Components from Simulants and Hanford Tank Sludge 241-S-110: Results of FY01 Studies

Description: This study addressed three aspects in selected alkaline leaching: first, the use of oxidants persulfate, permanganate, and ferrate as selective chromium-leaching agents from washed Hanford Tank S-110 solids under varying conditions of hydroxide concentration, temperature, and time was investigated. Second, the selective dissolution of solids containing mercury(II) oxide under alkaline conditions was examined. Various compounds were studied for their effectiveness in dissolving mercury under var… more
Date: September 10, 2002
Creator: Rapko, Brian M.; Vienna, John D.; Sinkov, Serguei I.; Kim, Jinseong & Cisar, Alan J.
Partner: UNT Libraries Government Documents Department
open access

Database and Interim Glass Property Models for Hanford HLW and LAW Glasses

Description: This report discusses a methodology for increasing the efficiency and decreasing the cost of vitrifying nuclear waste by optimizing waste-glass formulation. This methodology involves collecting and generating a property-composition database (for glass properties that determine waste-glass processability and acceptability) and relating these properties to glass composition via property-composition models. The report explains how the property-composition models are developed, fitted to data and e… more
Date: September 27, 2002
Creator: Vienna, John D.; Kim, Dong-Sang & Hrma, Pavel R.
Partner: UNT Libraries Government Documents Department
open access

Iron Phosphate Glass as an Alternative Waste-Form for Hanford LAW

Description: Although the current baseline Hanford flowsheet for immobilizing low-activity waste (LAW) assumes borosilicate-based glass, opportunities exist to improve or change this baseline to reduce the current schedule and cost requirements of accomplishing the mission of site cleanup. Development of an alternative glass-forming system can lead to this goal of cost and schedule reduction through enhanced waste loading and higher plant throughput. The purpose of this project is to investigate the iron-ph… more
Date: April 7, 2003
Creator: Kim, Dong-Sang (BATTELLE (PACIFIC NW LAB)); Buchmiller, William C. (BATTELLE (PACIFIC NW LAB)); Schweiger, Michael J. (BATTELLE (PACIFIC NW LAB)); Vienna, John D. (BATTELLE (PACIFIC NW LAB)); Day, D E.; Kim, C W. (Missouri, Univ Of - Rolla (For) et al.
Partner: UNT Libraries Government Documents Department
open access

Model for TCLP Releases from Waste Glasses

Description: A first-order property model for normalized Toxicity Characteristic Leaching Procedure (TCLP) release as a function of glass composition was developed using data collected from various studies. The normalized boron release is used to estimate the release of toxic elements based on the observation that the boron release represents the conservative release for those constituents of interest. The current TCLP model has two targeted application areas: (1) delisting of waste-glass product as radioac… more
Date: May 1, 2003
Creator: Kim, Dong-Sang & Vienna, John D.
Partner: UNT Libraries Government Documents Department
open access

Stability of High-Level Waste Forms

Description: The objective of the proposed effort is to use a new approach to develop solution models of complex waste glass systems and spent fuel that are predictive with regard to composition, phase separation, and volatility. The effort will also yield thermodynamic values for waste components that are fundamentally required for corrosion models used to predict the leaching/corrosion behavior for waste glass and spent fuel material. This basic information and understanding of chemical behavior can subse… more
Date: June 13, 2003
Creator: Besmann, Theodore M. & Vienna, John D.
Partner: UNT Libraries Government Documents Department
open access

Development and Testing of ICV Glasses for Hanford LAW

Description: Preliminary glass compositions for immobilizing Hanford low-activity waste (LAW) by the in-container vitrification (ICV) process were fabricated at crucible- and engineering-scale and tested at Pacific Northwest National Laboratory. This testing showed that glasses with LAW loading of 20 mass% can readily be made and meet all product constraints by a far margin. It was found that the response constraint of the vapor hydration test (VHT) of less than 50 g/(m2•d) alteration rate was the most rest… more
Date: August 1, 2003
Creator: Kim, Dong-Sang; Vienna, John D.; Hrma, Pavel R.; Schweiger, Michael J.; Matyas, Josef; Crum, Jarrod V. et al.
Partner: UNT Libraries Government Documents Department
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