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Test plan: Laboratory-scale testing of the first core sample from Tank 102-AZ

Description: The overall objectives of the Radioactive Process/Product Laboratory Testing (RPPLT), WBS 1.2.2.05.05, are to confirm that simulated HWVP feed and glass are representative of actual radioactive HWVP feed and glass and to provide radioactive leaching and glass composition data to WFQ. This study will provide data from one additional NCAW core sample (102-AZ Core 1) for these purposes.
Date: March 1, 1996
Creator: Morrey, E.V.
Partner: UNT Libraries Government Documents Department

Comparison of simulants to actual neutralized current acid waste: Process and product testing of three NCAW core samples from Tanks 101-AZ and 102-AZ

Description: A vitrification plant is planned to process the high-level waste (HLW) solids from Hanford Site tanks into canistered glass logs for disposal in a national repository. Programs have been established within the Pacific Northwest Laboratory Vitrification Technology Development (PVTD) Project to test and model simulated waste to support design, feed processability, operations, permitting, safety, and waste-form qualification. Parallel testing with actual radioactive waste is being performed on a laboratory-scale to confirm the validity of using simulants and glass property models developed from simulants. Laboratory-scale testing has been completed on three radioactive core samples from tanks 101-AZ and 102-AZ containing neutralized current acid waste (NCAW), which is one of the first waste types to be processed in the high-level waste vitrification plant under a privatization scenario. Properties of the radioactive waste measured during process and product testing were compared to simulant properties and model predictions to confirm the validity of simulant and glass property models work. This report includes results from the three NCAW core samples, comparable results from slurry and glass simulants, and comparisons to glass property model predictions.
Date: April 1, 1996
Creator: Morrey, E.V. & Tingey, J.M.
Partner: UNT Libraries Government Documents Department

Comparison of simulants to actual neutralized current acid waste: process and product testing of three NCAW core samples from Tanks 101-AZ and 102-AZ

Description: A vitrification plant is planned to process the high-level waste (HLW) solids from Hanford Site tanks into canistered glass logs for disposal in a national repository. Programs were established within the Pacific Northwest Laboratory Vitrification Technology Development (PVTD) Project to test and model simulated waste to support design, feed processability, operations, permitting, safety, and waste-form qualification. Parallel testing with actual radioactive waste was performed on a laboratory-scale to confirm the validity of using simulants and glass property models developed from simulants. Laboratory-scale testing has been completed on three radioactive core samples from tanks 101-AZ and 102-AZ containing neutralized current acid waste (NCAW), which is one of the first waste types to be processed in the high-level waste vitrification plant under a privatization scenario. Properties of the radioactive waste measured during process and product testing were compared to simulant properties and model predictions to confirm the validity of simulant and glass property ,models work. This report includes results from the three NCAW core samples, comparable results from slurry and glass simulants, and comparisons to glass property model predictions.
Date: October 1, 1996
Creator: Morrey, E.V.; Tingey, J.M. & Elliott, M.L.
Partner: UNT Libraries Government Documents Department

Offgas characterization from the radioactive NCAW core sample (102-AZ-C1) and simulant during HWVP feed preparation testing: Letter report

Description: The primary objective of the Radioactive Process/Product Laboratory Testing (RPPLT) is to provide preliminary confirmation that the nonradioactive waste feed stimulant recipe is adequate for addressing the testing needs of design, safety, waste form qualification (WFO), and permitting of the Hanford Waste Vitrification Plant HWVP). The information contained In this letter report specifically addresses offgas production during the formating, digestion, and recycle addition of the third Neutralized Current Acid Waste (NCAW) core sample and core stimulant. Testing was conducted using a laboratory-scale version of the HWVP flowsheet.
Date: March 1, 1996
Creator: Langowski, M.H.; Morrey, E.V.; Tingey, J.M. & Beckette, M.R.
Partner: UNT Libraries Government Documents Department

Laboratory-scale vitrification and leaching of Hanford high-level waste for the purpose of simulant and glass property models validation

Description: The Hanford Waste Vitrification Plant (HWVP) is being built to process the high-level and TRU waste into canistered glass logs for disposal in a national repository. Testing programs have been established within the Project to verify process technology using simulated waste. A parallel testing program with actual radioactive waste is being performed to confirm the validity of using simulates and glass property models for waste form qualification and process testing. The first feed type to be processed by and the first to be tested on a laboratory-scale is pretreated neutralized current acid waste (NCAW). The NCAW is a neutralized high-level waste stream generated from the reprocessing of irradiated nuclear fuel in the Plutonium and Uranium Extraction (PUREX) Plant at Hanford. As part of the fuel reprocessing, the high-level waste generated in PUREX was denitrated with sugar to form current acid waste (CAW). Sodium hydroxide and sodium nitrite were added to the CAW to minimize corrosion in the tanks, thus yielding neutralized CAW. The NCAW contains small amounts of plutonium, fission products from the irradiated fuel, stainless steel corrosion products, and iron and sulfate from the ferrous sulfamate reductant used in the PUREX process. This paper will discuss the results and status of the laboratory-scale radioactive testing.
Date: February 1, 1993
Creator: Morrey, E.V.; Elliott, M.L. & Tingey, J.M.
Partner: UNT Libraries Government Documents Department

Radioactive waste vitrification offgas analysis proposal

Description: Further validation of the Hanford Waste Vitrification Plant (HWVP) feed simulants will be performed by analyzing offgases during crucible melting of actual waste glasses and simulants. The existing method of vitrifying radioactive laboratory-scale samples will be modified to allow offgas analysis during preparation of glass for product testing. The analysis equipment will include two gas chromatographs (GC) with thermal conductivity detectors (TCD) and one NO/NO{sub x} analyzer. This equipment is part of the radioactive formating offgas system. The system will provide real-time analysis of H{sub 2}, O{sub 2}, N{sub 2}, NO, N{sub 2}O, NO{sub 2}, CO, CO{sub 2}, H{sub 2}O, and SO{sub 2}. As with the prior melting method, the product glass will be compatible with durability testing, i.e., Product Consistency Test (PCT) and Material Characterization Center (MCC-1), and crystallinity analysis. Procedures have been included to ensure glass homogeneity and quenching. The radioactive glass will be adaptable to Fe{sup +2}/{Sigma}Fe measurement procedures because the atmosphere above the melt can be controlled. The 325 A-hot cell facility is being established as the permanent location for radioactive offgas analysis during formating, and can be easily adapted to crucible melt tests. The total costs necessary to set up and perform offgas measurements on the first radioactive core sample is estimated at $115K. Costs for repeating the test on each additional core sample are estimated to be $60K. The schedule allows for performing the test on the next available core sample.
Date: November 1, 1993
Creator: Nelson, C. W. & Morrey, E. V.
Partner: UNT Libraries Government Documents Department