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Radioactive Demonstration of Mineralized Waste Forms Made from Hanford Low Activity Waste (Tank SX-105, Tank AN-103, and AZ-101/102) by Fluidized Bed Steam Reformation (FBSR)

Fluidized Bed Steam Reforming (FBSR) is a robust technology for the immobilization of a wide variety of radioactive wastes. Applications have been tested at the pilot scale for the high sodium, sulfate, halide, organic and nitrate wastes at the Hanford site, the Idaho National Laboratory (INL), and the Savannah River Site (SRS). Due to the moderate processing temperatures, halides, sulfates, and technetium are retained in mineral phases of the feldspathoid family (nepheline, sodalite, nosean, carnegieite, etc). The feldspathoid minerals bind the contaminants such as Tc-99 in cage (sodalite, nosean) or ring (nepheline) structures to surrounding aluminosilicate tetrahedra in the feldspathoid structures. The granular FBSR mineral waste form that is produced has a comparable durability to LAW glass based on the short term PCT testing in this study, the INL studies, SPFT and PUF testing from previous studies as given in the columns in Table 1-3 that represent the various durability tests. Monolithing of the granular product was shown to be feasible in a separate study. Macro-encapsulating the granular product provides a decrease in leaching compared to the FBSR granular product when the geopolymer is correctly formulated.

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Exploring Engineering Control through Process Manipulation of Radioactive Liquid Waste Tank Chemical Cleaning

One method of remediating legacy liquid radioactive waste produced during the cold war, is aggressive in-tank chemical cleaning. Chemical cleaning has successfully reduced the curie content of residual waste heels in large underground storage tanks; however this process generates significant chemical hazards. Mercury is often the bounding hazard due to its extensive use in the separations process that produced the waste. This paper explores how variations in controllable process factors, tank level and temperature, may be manipulated to reduce the hazard potential related to mercury vapor generation. When compared using a multivariate regression analysis, findings indicated that there was a significant relationship between both tank level (p value of 1.65x10 -23 ) and temperature (p value of 6.39x10 -6 ) to the mercury vapor concentration in the tank ventilation system. Tank temperature showed the most promise as a controllable parameter for future tank cleaning endeavors. Despite statistically significant relationships, there may not be confidence in the ability to control accident scenarios to below mercury’s IDLH or PAC-III levels for future cleaning initiatives.

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Radioactive demonstration of final mineralized waste forms for Hanford waste treatment plant secondary waste (WTP-SW) by fluidized bed steam reforming (FBSR) using the bench scale reformer platform

The U.S. Department of Energy’s Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford’s tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as 137Cs, 129I, 99Tc, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150°C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW.

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Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229 Th, 230 Th, 232 U, 233 U, and 234 U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

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Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

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Nevada National Security Site 2015 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

This report is a compilation of the groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada National Security Site, Nye County, Nevada. Groundwater samples from the aquifer immediately below the Area 5 RWMS have been collected and analyzed and static water levels have been measured in this aquifer since 1993. This report updates these data to include the 2015 results. Analysis results for leachate contaminants collected from the mixed-waste cell at the Area 5 RWMS (Cell 18) are also included.

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International Approaches for Nuclear Waste Disposal in Geological Formations: Geological Challenges in Radioactive Waste Isolation—Fifth Worldwide Review

The overall objective of the Fifth Worldwide Review (WWR-5) is to document the current state-of-the-art of major developments in a number of nations throughout the World pursuing geological disposal programs, and to summarize challenging problems and experience that have been obtained in siting, preparing and reviewing cases for the operational and long-term safety of proposed and operating nuclear waste repositories. The scope of the Review is to address current specific technical issues and challenges in safety case development along with the interplay of technical feasibility, siting, engineering design issues, and operational and post-closure safety. In particular, the chapters included in the report present the following types of information: the current status of the deep geological repository programs for high level nuclear waste and low- and intermediate level nuclear waste in each country, concepts of siting and radioactive waste and spent nuclear fuel management in different countries (with the emphasis of nuclear waste disposal under different climatic conditions and different geological formations), progress in repository site selection and site characterization, technology development, buffer/backfill materials studies and testing, support activities, programs, and projects, international cooperation, and future plans, as well as regulatory issues and transboundary problems.

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2016 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) within the Nevada National Security Site (NNSS). These data include direct radiation exposure, as well as radiation from the air, groundwater, meteorology, and vadose zone. This report summarizes the 2016 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports, developed by National Security Technologies, LLC Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show that tritium concentrations in water vapor and americium and plutonium concentrations in air particles are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. During 2016, precipitation at the Area 3 RWMS was 8% below average, and precipitation at the Area 5 RWMS was 8% above average. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation as measured from the bare-soil weighing lysimeter. Vadose zone monitoring on Area 5 and Area 3 RWMS cell covers shows no evidence of precipitation percolating through the covers to the waste. Moisture from precipitation did not percolate below 150 centimeters (cm) (5 feet [ft]) in the vegetated final cover on the U-3ax/bl disposal unit at the Area 3 RWMS. During 2016, there was no drainage through 2.4 meters (8 ft) of soil as indicated from the Area 3 drainage lysimeters that received only natural precipitation. Forty-four percent of the applied precipitation and irrigation drained from the bare-soil drainage lysimeter, which received 3 times the natural precipitation. All 2016 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facilities’ PAs

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Unreviewed Disposal Question Evaluation: Impact of Delayed Revegetation of Closure Covers at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This Unreviewed Disposal Question Evaluation (UDQE) assesses the impacts of delayed revegetation of the 92-acre (ac) Low-Level Waste Management Unit (LLWMU) closure covers in the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The Area 5 RWMS Performance Assessment (PA) assumes closure with fully functional evapotranspiration (ET) covers. A key safety function of ET covers is to prevent percolation of water through waste by absorbing and storing precipitation in near-surface soil until it is returned to the atmosphere by ET. The closure cover’s ET function relies heavily on native desert vegetation to transpire moisture from dry soils. Final ET closure covers were installed on the 92-ac LLWMU in 2012. Since then attempts to reestablish native vegetation on the closure covers have failed. As of 2018, perennial native vegetation is mostly absent on the covers, but a dense population of invasive weeds (e.g., Salsola paulsenii and Halogeton glomeratus) is present. This UDQE assesses the effect of delayed restoration of native desert vegetation on the hydrologic performance of the Area 5 RWMS ET covers.

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Spent Nuclear Fuel and High-Level Radioactive Waste Inventory Report

This report provides information on the inventory of commercial spent nuclear fuel (SNF), as well as Government-managed SNF and high-level radioactive waste (HLW). Actual or estimated quantitative values for current inventories are provided along with inventory forecasts derived from examining different future commercial nuclear power generation scenarios.

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Unreviewed Disposal Question Evaluation: Disposal of the Nevada National Security Site Uranium Powder at the Area 5 Radioactive Waste Management Site, Nevada National Security Site

This Unreviewed Disposal Question Evaluation (UDQE) assesses whether the Nevada National Security Site (NNSS) Uranium Powder (Normal, depleted uranium [DU], low-enriched uranium [LEU]) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site.

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Unreviewed Disposal Evaluation Question: Disposal of the Idaho National Laboratory Waste Associated with the Unirradiated Light Water Breeder Reactor at the Area 5 Radioactive Waste Management Site

This Unreviewed Disposal Question Evaluation (UDQE) assesses whether the Idaho National Laboratory (INL) Waste Associated with the Unirradiated Light Water Breeder Reactor (LWBR) waste stream (INL167203QR1, Revision 1 [INL 2017]) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS).

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Functions and Requirements of the Radioactive Waste Test Platform

The purpose of this document is to provide the function and requirements for the Radioactive Waste Test Platform (hereafter called “test platform”). Historically, testing has been performed at the bench scale with actual waste samples (Fiskum et al. 2006a, b, 2008, 2009; Lumetta et al. 2009; Edwards et al. 2009; Smith et al. 2000, 2001). These tests form the basis for waste treatment operations at the Hanford Site. However, since 2008, there has been limited capability to perform bench-scale tests with actual waste samples. Prior work has shown that simulants can provide useful information about the performance of unit operations; however, there have been examples in the past where simulants did not adequately capture the expected performance of the tank waste materials. Therefore, as the Hanford Site moves towards initiating treatment of tank waste, it is important to have a platform available that can evaluate process options utilizing tank waste samples. This platform can be utilized to evaluate processing options and to address troubleshooting for unexpected system performance. The initial operations for the test platform will be to contribute towards maturing the Direct Feed Low-Activity Waste (DFLAW) feed qualification program and to demonstrate an option for disposition of the melter offgas stream. This equipment will be the ideal platform to evaluate additional process options including filtration operating conditions associated with precipitation, methods to extend resin lifetime associated with multi-cycle degradation, and evaluation of other approaches to minimize the impact of recycle streams from the effluent management system (including Tc) on melter performance.

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Special Analysis for the Disposal of the Portsmouth Uranium Fluoride Solids Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis (SA) evaluates whether the Portsmouth Gaseous Diffusion Plant (PORT) Uranium (U) Fluoride Solids waste stream is suitable for disposal by shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site (NNSS). The PORT U Fluoride Solids waste stream consists of highly enriched uranium solids. The PORT U Fluoride Solids waste stream requires an SA to resolve whether it is acceptable to dispose of technetium-99 ( 99 Tc), uranium-234 ( 234 U), and thorium-230 ( 230 Th) with activity concentrations exceeding the NNSS Waste Acceptance Criteria Action Levels.

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Special Analysis for the Disposal of Sandia National Laboratory Line Generated Waste at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis report evaluates whether the Sandia National Laboratory (SNL) Line Generated Waste is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the SNL Line Generated waste meets all DOE M 435.1-1 performance objectives.

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Special Analysis for the Disposal of the Idaho National Laboratory U-233 Solidified Grinding Sludge and Associated Debris Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis report evaluates whether the Idaho National Laboratory (INL) Uranium-233 (233U) Solidified Grinding Sludge and Associated Debris waste stream is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the INL 233U Solidified Grinding Sludge waste meets all DOE M 435.1-1 performance objectives. The INL 233U Solidified Grinding Sludge waste stream is recommended for acceptance with the condition that the total 233U inventory shall not exceed 2.3E13 Bq.

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Unreviewed Disposal Question Evaluation: Disposal of the Transuranic Waste Processing Center Low-Level Waste at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This Unreviewed Disposal Question Evaluation assesses whether the Transuranic Waste Processing Center (TWPC) Low-Level waste stream is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the TWPC Low-Level Waste meets all DOE M 435.1-1 performance objectives. The TWPC Low-Level Waste stream is recommended for acceptance without conditions.

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Unreviewed Disposal Question Evaluation: Disposal of the Materials & Energy Corporation Regulated Asbestos Mixed Low-Level Waste Macroencapsulated Debris at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This Unreviewed Disposal Question Evaluation assesses whether the Materials and Energy Corporation (M&EC) Regulated Asbestos Mixed Low-Level Waste (MLLW) Macroencapsulated Debris waste stream is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the M&EC Regulated Asbestos MLLW Macroencapsulated Debris Waste meets all DOE M 435.1-1 performance objectives. The M&EC Regulated Asbestos MLLW Macroencapsulated Debris waste stream is recommended for acceptance without conditions.

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