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Viragh, Charles

Publications and source records attributed to Viragh, Charles.

DuraMelter 100 Sub-Envelope Changeover Testing Using LAW SubEnvelopes A1 and C1 Feeds in Support of the LAW Pilot Melter (Final Report)

The primary goal of the testing described in this report was to develop and recommend a compliant HLW glass formulation to support the actual waste testing of AZ-101 Envelope D waste (blended with actual pretreatment products including Cs- and Tc-eluates from pretreatment of AP-101 and AZ-101 LAW). Testing of actual waste will be performed at Battelle, Pacific Northwest Division. The test objective was met by the development and recommendation of the glass formulation HLW98-95; the formulation has been transmitted to the WTP to support vitrification of HLW AZ-101 actual waste.

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FY2021 ILAW Glass Ion-Exchange Rate Testing

Approximately 54 to 56 million gallons of radioactive mixed waste is currently stored in underground tanks at The United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High-Level Waste (IHLW) products. The ILAW product will be disposed of in an engineered facility – the Integrated Disposal Facility (IDF) – on the Hanford site, while the IHLW product will be directed to the national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. To capitalize on the success of the FY19 and FY20 Atkins/VSL test results on six glasses, Washington River Protection Solutions, LLC (WRPS) has contracted with Atkins/VSL to collect IEX data on four more ILAW glasses using PFT, the results of which are the subject of the present report. The work described herein was performed according to a Test Plan that is responsive to the corresponding WRPS scope of work.

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ILAW Glass Ion-Exchange Rate Testing (Final Report FY2020)

About 50 million gallons of high-level mixed waste is currently stored in underground tanks at The United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High-Level Waste (IHLW) products. The ILAW product will be disposed of in an engineered facility – the Integrated Disposal Facility (IDF) – on the Hanford site, while the IHLW product will be directed to the national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal.

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FY2019 ILAW Glass Ion Exchange Rate Testing (Final Report)

About 50 million gallons of high-level mixed waste is currently stored in underground tanks at The United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High-Level Waste (IHLW) products. The ILAW product will be disposed of in an engineered facility - the Integrated Disposal Facility (IDF) - on the Hanford site, while the IHLW product is designed for acceptance into a national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal.

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FY2018 ILAW Glass SPFT Testing for Disposal at IDF: Glasses ORLEC46 and ORLEC52 (Final Report, Rev. 0)

About 50 million gallons of high-level mixed waste is currently stored in underground tanks at The United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility – the Integrated Disposal Facility (IDF) – on the Hanford site, while the IHLW product is designed for deep geological disposal in a national facility for high level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. The objective of the work described in this report is to perform testing, data collection, and analyses for the ILAW glass product for subsequent use in the performance assessment (PA) of the IDF to assess potential environmental risks associated with long-term storage.

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Redox Control for Processing of High-Bi HLW (VSL-18R4400-1, Rev. 0)

This report provides results from tests designed to determine the redox conditions associated with bismuth reduction and the potential for molten bismuth metal formation in a high-Bi HLW glass melt, its role in Inconel metal corrosion, and to identify feed reductant and oxidant contents to avoid issues during melter feed processing. This was accomplished through crucible scale tests and with DM10 melter system tests using simulated high bismuth HLW and a glass composition that performed well during crucible scale and DM100 melter testing.

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FY2017 ILAW Glass SPFT Testing for Disposal at IDF: Glass IDF21-EC14

About 50 million gallons of high-level mixed waste is currently stored in underground tanks at The United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility – the Integrated Disposal Facility (IDF) – on the Hanford site, while the IHLW product is designed for deep geological disposal in a national facility for high level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. The objective of the work described in this report is to perform testing, data collection, and analyses for the ILAW glass product for subsequent use in the performance assessment (PA) of the IDF to assess potential environmental risks associated with long-term storage.

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Effect of the Form of Iron on HLW Melt Rate

The primary objective of the work reported herein was to determine the effect of the form of iron in the HLW stream on feed processing rate. Secondary objectives were to determine the effect of iron form on feed properties, glass properties, and carryover from the melter during vitrification. This was accomplished by replacing the Fe(OH) 3 used in a previously tested simulant for C-106/AY-102 actual waste with either goethite (FeO(OH)), hematite (Fe 2 O 3 ), magnetite (Fe 3 O 4 ), or a mixture of iron oxides, and processing the resulting melter feeds on the DM100 melter system. Glass forming additives were combined with the high iron simulant to produce melter feed targeting the HLW-NG-Fe2 glass composition. Melter feed samples also underwent testing for rheological properties and processing rate using a VGF system.

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Vitrification Tests with Potential Technetium Capture Streams

About 50 million gallons of high-level waste is currently stored in underground tanks at The United States Department of Energy’s (DOE’s) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE’s Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility on the Hanford site while the IHLW product is designed for acceptance at a national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. The Low Activity Waste (LAW) and High-Level Waste (HLW) at Hanford will be vitrified in Joule Heated Ceramic Melters (JHCMs) to produce stable products for disposal. Technetium is an important radioactive component in the Hanford tank waste and is typically one of the principal contributors to risk in performance assessments for the ILAW disposal facility. Technetium is also one of the more volatile radionuclides and the retention of technetium in the glass under the high temperature conditions prevailing during vitrification can vary over a relatively wide range depending on the feed composition, feed chemistry, and melter operating parameters. In support of the WTP Project, the Vitreous State Laboratory (VSL) at The Catholic University of America (CUA) and EnergySolutions have developed and tested glass formulations for WTP waste envelopes to provide data to meet the WTP contract requirements and to support system design activities. That work is based upon small-scale batch melts (“crucible melts”) using waste simulants. Glass compositions suitable for processing the tank waste streams for the WTP have been identified and tested for processing and product quality requirements at various scales, ranging from crucible melts of a few grams, up to the LAW Pilot Melter at processing rates in excess of 6600 kg/day (2000 kg/m 2 /day). Recent testing performed at VSL for Washington River Protection Solutions, LLC (WRPS) has investigated the baseline “single-pass” retention of technetium over the range of WTP LAW feed compositions and glass formulations as well as the development of potential modifications to the baseline that could increase the single-pass retention. For the WTP melter systems, the liquid waste streams from the primary off-gas system components are recycled back to the pretreatment facility and, ultimately, to subsequent melter feed batches. Such a recycle loop can greatly increase the overall retention of volatile constituents in the glass product over the single-pass value. Accordingly, more recent testing at VSL has been conducted on a melter system that incorporates a recycle flow sheet. The results from that work have provided important performance data for the unit operations in the primary off-gas system with respect to technetium capture and recycle, which is crucial in assessing the amount of technetium that ultimately reports to non-glass waste forms.

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