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Methodology for Volume Reduction of Radioactive Metallic Waste - 19491

A decontamination methodology for out-of-core nuclear reactor alloys is being developed to reduce the volume of low- and intermediate-level radioactive metallic wastes. For out-of-core reactor metals contamination is limited to surface oxides. For surface oxide removal a technology based on laser ablation is being explored. This paper presents work performed to identify the key parameters that affect the efficiency of removal of surface oxides from out-of-core reactor metals and alloys. This study examined carbon steel (used for coolant feeder pipes of CANDU{sup R} reactors) as a model reactor material. The morphology and thickness of oxides on a used feeder pipe vary considerably depending on its service life and the location along the pipe. Hence, oxides with different morphologies and thicknesses were first grown by corroding carbon steel coupons under different solution conditions. The oxides formed ranged from thin layers of uniformly distributed mixed Fe{sup II}/Fe{sup III} hydroxides/oxides to dual layers consisting of ferric oxide/oxyhydroxide islands with thickness up to 200 μm on top of the more uniformly distributed mixed Fe{sup II}/Fe{sup III} layer. Removal of these oxides was performed using a 1064 nm pulsed laser. Of the laser parameters tested, the pulse radiance was found to be the most important. Four radiances ranging from 5 to 200 MW/cm{sup 2} were used. At radiances higher than 100 MW/cm{sup 2}, single pulses were sufficient to remove both types of oxides, but also extensively melted the metal substrate. At lower radiances, multiple pulses were required to remove the oxides completely, but caused less damage to the metal substrate. (authors)

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Design of an Evapotranspiration Surface Barrier for the Subsurface Disposal Area at INL - 19220

At the INL Site, the US DOE is planning to construct one of its largest CERCLA landfill covers. An evapotranspiration surface barrier that will be approximately 65 ha (160 acres) will cover the 39-ha (97-acre) Subsurface Disposal Area at the INL to isolate legacy mixed waste disposed of prior to 1988, low-level radioactive waste disposed of after 1988, and debris from demolition of structures being used to process some of the legacy mixed waste. The evapotranspiration surface barrier will limit percolation to less than 1 cm (0.39 in.) per year under typical precipitation conditions; provide a minimum 3-m (10-ft)-thick cover over all waste to minimize the potential for plant, animal, and inadvertent human intrusion; support growth of native vegetation; and visually blend in with the surrounding desert landscape. A robust design will allow the evapotranspiration surface barrier to resist erosion and perform for a minimum of 1,000 years. The 1-cm (0.39-in.)-per-year and 1,000-year performance objectives were established by a CERCLA record of decision and its implementing remedial design work plan, and these performance objectives are consistent with a performance assessment conducted under US DOE Order 435.1, 'Radioactive Waste Management.' (authors)

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Disposal for Canada... a Responsible Solution for 120 years of Waste Generation - 17052

Disposal is coming to Canada. After decades of interim storage of radioactive wastes, Canadian Nuclear Laboratories (CNL) is preparing to build Canada's first facility for the permanent disposal of low-level and other suitable radioactive wastes that satisfy the waste acceptance criteria. A project was launched in 2015 to establish a Near Surface Disposal Facility (NSDF) and to place it into operation in 2020 for 50 years. (authors)

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The Utility of Waste Tank Historical Reviews in Bulk Waste Removal Operations at the Savannah River Site – 25271

SRMC is actively working to remove, treat, and dispose radioactive waste generated by the separation facilities at SRS since their initial operations in the 1950s. The separation facilities at SRS have produced nuclear materials for a variety of purposes, particularly national defense, and continue to support the disposition of spent fuel through the Accelerated Basin Deinventory program. In almost 70 years of operation, nearly 625,000 m3 (165 million gallons) of radioactive waste have been generated and transferred to the tank farm facilities at SRS [1]. As a result of volume reduction (e.g., evaporation) and waste solidification (e.g., vitrification), approximately 127,000 m3 (33.5 million gallons) of material remain as of June 30, 2024 [2]. This liquid waste has since been stored in 51 large underground waste tanks present on the site. These waste tanks may contain up to 4,921 m3 (1.3 million gallons) of radioactive waste each in the form of saltcake or sludge. SRMC’s contract is to treat and dispose of this waste, clean the tanks, and operationally close them. To date, 8 of the 51 waste tanks have been operationally closed. Waste retrieval and tank closure activities are ongoing in an additional 17 tanks through either operations in the field or in design [3].

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Innovative Waste Packaging and Associated Venting/Hydrogen Management - 16594

The original strategy for managing intermediate level waste (ILW) was developed in the 1980s by the UK Nuclear Industry Radioactive Waste Executive (NIREX), which is now the Radioactive Waste Management Limited (RWM), a wholly owned subsidiary of the Nuclear Decommissioning Authority (NDA). The strategy involved retrieving ILW, sorting and encapsulating it in cement based grout within thin walled stainless steel containers. The containers would then be transferred to a large purpose-built shielded ILW store on site, where they would be stored until the planned final deep geological disposal facility becomes available. In recognition of the high up-front costs of such a strategy, which requires remote facilities for the encapsulation and storage, and coupled with the long programme duration for the design, construction and commissioning of these facilities, waste management organisations responsible for managing the clean-up of legacy facilities within the UK have, in recent years, sought innovative solutions which could potentially both accelerate clean-up and hazard reduction on sites, and with a lower overall programme lifecycle cost. Many of the recent innovative solutions are focused around a new family of packaging designs known as robust shielded containers (RSCs). These are self-shielded containers manufactured from materials such as ductile cast iron or fabricated steel. These containers offer the potential to package wastes for disposal without encapsulation and avoid the need for a highly engineered remote handled shielded store for interim storage. The paper provides a high level overview of the generic concepts of RSCs developed by Croft and focuses on the specific challenges of wasteform evolution on waste package integrity and performance. In particular, the integrity and performance of the filtered vent system required to manage internal pressurisation and to ensure sufficient venting capacity of hydrogen and other evolved gases. The paper summarises the analysis by ARUP undertaken to substantiate the RSC integrity under detonation/deflagration explosion loadings arising from hydrogen accumulation. Analyses of the structural response of the filter assembly were undertaken for both detonation and deflagration explosion scenarios, with the loadings applied to the filter housing rim and to the filter vent cover. The paper also presents evidence of the mechanical performance of the filter medium in terms of pressure transients during deflagration events and the degree to which filtration efficiency is maintained. (authors)

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Panel Session 75: US NRC - Current and Emerging US NRC Regulatory Topics

The panel addressed several current and emerging NRC regulatory issues impacting the radioactive waste arena. The panelists provided different perspectives on several key issues such as the revision of 10 CFR Part 61, scoping study on very low-level waste and consolidated interim storage of spent nuclear fuel among other timely regulatory topics. Co-Chairs, John Tappert and Larry Camper, introduced the session panel members and provided a summary of the purpose of the session. The panel focused on several current and emerging US NRC regulatory issues impacting the radioactive waste arena and stakeholders. The panelists provided different perspectives on several key regulatory issues such as: the revision of 10CFR Part 61, the Greater-than-Class C (GTCC) and Transuranic (TRU) waste disposal, coping with studies on very low-level waste and waste classification system, as well as other timely regulatory topics. Presentations proposed include: 1 - Overview of NRC Low-Level Radioactive Waste Activities and Initiatives (Christepher McKenney, US NRC (USA)); 2 - Is the Grass Really Greener? Canadian Regulatory Perspective (Karine Glenn, Canadian Nuclear Safety Commission (Canada)); 3 - EPRI Perspectives on 10CFR61 Revision (Lisa Edwards, EPRI (USA)); 4 - State of Nuclear Industry and Radwaste Management (Janet Schlueter, Nuclear Energy Institute (USA)); 5 - Concrete Steps the U.S. NRC Can Take to Improve LLW Disposal (Tom Magette, Talisman International (USA))

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Panel Session 3: Featured Country Canada: Management and Disposal of High and Low-Level Waste

This panel featured Senior Executives accountable for the safe management and disposal of most of Canada's radioactive waste liabilities and provided their perspectives on current plans and progress made to date. Topics addressed by the panelists included national policies and programs, the regulatory framework, and actions led by the waste generators and solution implementers to ensure Canada's waste legacy is responsibly managed. Presentations proposed include: 1 - Overview of Canadian Radioactive Waste Policy and Long-Term Waste Management Projects (Dave McCauley, Natural Resources Canada (Canada)); 2 - Featured Country: Canada - National Repository (Laurie Swami, Nuclear Waste Management Organization (Canada)); 3 - Management and Disposal of Ontario Power Generation's Low and Intermediate Level Waste (Lise Morton, Ontario Power Generation (Canada)); 4 - Featured Country: Canada - National Laboratories Liabilities (Richard Sexton, Atomic Energy of Canada Limited (Canada)); 5 - Management and Disposal of High and Low-Level Waste (Mark Lesinski, Canadian Nuclear Laboratories (Canada)); 6 - Disposal in Canada: The Regulatory Perspective (Ramzi Jammal, Canadian Nuclear Safety Commission (Canada))

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EPRI Project Update on International Nuclear Power Plant Waste Classification - 16224

Countries around the globe use varying schemes for the characterization of radioactive waste. Many countries use adaptations of the International Atomic Energy Agency (IAEA) waste classification scheme. Other countries use the Class A, B, and C waste classification scheme that was developed in the United States. General comparisons have been made between the IAEA and the United States (U.S.) classification schemes, but a clear and well researched comparison of the two schemes was not evident in the available research data sets. The Electric Power Research Institute (EPRI) Radiation Safety (RS) Program has conducted a technical evaluation that compares these two waste characterization schemes. EPRI developed a set of reference wastes that are representative of nuclear power plant low-level radioactive waste in form and radioactivity concentrations (e.g. dry active waste, high activity resin, low activity resin, high activity filters and low activity filters). These reference wastes were then classified using the waste classification systems in place in several countries around the world. This paper and presentation will provide a summary of that research, show where strong comparisons and correlations can be made, and provide a discussion on how this information might inform the harmonization of global waste classification standards. (authors)

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Communicating Technical Information: Different Approaches for Different Audiences - 19399

The Canadian Nuclear Safety Commission (CNSC), Canada's independent nuclear regulator, has a 70- year history of regulating nuclear safety in Canada. Part of the CNSC's mandate is to disseminate objective scientific, technical and regulatory information to the public. The CNSC prides itself on being transparent with the public, and openly sharing scientific, technical and regulatory information on its regulatory activities with stakeholders. We value the public's feedback, and have a robust public participation program to allow for public involvement in the CNSC's activities. However, different audiences have different needs based on their level of technical knowledge and expertise. The CNSC's experience with stakeholder interactions has demonstrated the need to balance the dissemination of technical information through different communication platforms, in order to satisfy the needs of various intended audiences. This paper will focus on the radioactive waste management communications methods that the CNSC has implemented for two distinct audiences: 1. Audiences with little or no technical background: Communications with this audience requires techniques to make highly technical concepts more understandable. The focus is on educating about matters related to radioactive waste management, and informing about the safety aspects behind the regulation of radioactive waste. 2. Audiences with previous knowledge and experience with nuclear matters: Communications with this audience requires techniques to ensure that as much technical information and data as possible is available to inform stakeholders. The focus is on giving access to studies, research and raw data, in order to allow this audience to inform themselves, and potentially bring new perspectives to the CNSC's attention that could be used in regulatory oversight activities. In its capacity to disseminate scientific and technical information to the public as required by legislation, the CNSC holds a unique position compared with other Canadian regulatory bodies. The CNSC is one of the only Canadian regulators which: - Has a public hearing process which enables the public and Indigenous groups to express their issues and concerns directly to the decision-maker (the Commission) - Publishes regular regulatory oversight reports (report card on industry) that assess the safety performance of all its licensees - Publishes responses to all public comments received during consultation periods in our environmental assessment processes as well as our regulatory framework processes, including draft regulatory documents, discussions papers and proposed regulations - Has an independent environmental monitoring program, allowing the public access to environmental data. The program also seeks public and Indigenous input with respect to proposed environmental sampling campaigns, including suggestions on the samples to be taken and sampling locations. (authors)

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Solidification technology for organic liquid waste combined with solid materials from Cernavoda NPP, Romania - 16453

Canadian Deuterium Uranium (CANDU{sup R}) reactor designs were initially developed in the late 1950's and 1960's by the Atomic Energy of Canada Limited (AECL) in partnership with Ontario Power Generation. CANDU{sup R} 6 reactors are Pressurized Heavy Water Reactors (PHWRs), with an integrated containment system and are designed as either multi or single unit systems. Two single CANDU 6 systems are currently operating at Cernavoda with an additional two units expected to be brought online in the near future. The radioactive waste produced by the plant is currently stored in a waste interim storage facility located on-site. The main sources of radioactive waste in a CANDU plant are: - Primary Heat Transport (PHT) systems, - Moderator systems, - Other sources of radionuclides. The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. During the operation of the Cernavoda NPP, a series of waste streams have been generated for waste treatment purposes. One important waste stream is the combination of solid materials and liquid organic waste, creating flammable solids. Flammable solids represent solid materials, such as cloth, plastic, contaminated with oil containing gamma nuclides and H-3 from maintenance activities. This paper explores a method to solve the problem of liquid residues on solid materials by the application of absorbent materials. The existence of liquid residues on solid materials is a common problem at nuclear power stations globally. The primary issue centers on an effective method of eliminating the liquid to allow for the final acceptance and disposal of the solid waste by regulators. (authors)

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Thermal Process Technology for Nuclear Applications - 20379

ANSTO's Synroc technology has been developed to provide a safe, secure matrix for the immobilization and final disposal of radioactive waste. Synroc technology will be used to manage radioactive wastes from the production of the radioisotope Molybdenum-99 (Mo-99). This paper shall outline various stages of the process development with specific reference to the thermal treatment technology of calcination. Calcination is a key step in the Synroc process [1-2].The rotary thermal processing system includes: an advanced heating element design for increased robustness and ease of remote operation and maintenance, an enhanced modular design of components for ease of remote maintenance in a hot cell and in compliance with hot cell radioactive environment requirements for safety, reliability and maintainability. In addition to thermal treatment of waste from nuclear medicine production, this technology provides solutions for a variety of nuclear materials processing applications including sintering UO{sub 2} pellets for reactor fuel rods, oxidation of UO{sub 2} pellets, swarf, and powder to U{sub 3}O{sub 8}, de-nitration of Uranyl nitrate and hydrofluorination of UO{sub 2} pellets. The paper will also discuss thermal processing solutions for a range of nuclear applications. (authors)

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Panel Session 14: US NRC - Current and Emerging US NRC Regulatory Topics

This panel focused on several current and emerging US Nuclear Regulatory Commission (NRC) regulatory issues impacting the commercial radioactive waste arena in the US. The panelists provided different perspectives on key issues such as the revision of 10 Code of Federal Regulations Part 61 'Licensing Requirements For Land Disposal Of Radioactive Waste', the scoping study on very low-level waste, the consolidated interim storage of spent nuclear fuel and other timely regulatory topics. Panelists with presentations: Overview of NRC Low-Level Radioactive Waste Activities and Initiatives (Patricia Holahan); US Nuclear Power Plant Waste Management - US LLW Disposal Issues (Joe Weismann); Decommissioning Rule (Vern C. Rogers); What is TRU? Definition, Legislation, and Rulemaking (David Carlson); LLRW Regulatory Topics of Interest in Texas (Bobby Janecka); International Low Level Waste Management Practices (Richard McGrath)

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The U.S. Nuclear Waste Technical Review Board Intern Program: Developing Next Generation Nuclear Waste Professionals - 16102

The U.S. Nuclear Waste Technical Review Board (Board) created an internship program in the fall of 2013 for undergraduate and graduate students interested in management and disposal of spent nuclear fuel and high-level radioactive waste. Interns must select a project topic in a technical area related to the Board's mission and prepare a well-supported briefing for the agency. The ability to review technical and scientific information in a critical and unbiased manner is essential for completion of the intern's project and this is a particular focus of the interaction between the mentor and the intern. The interns from 2014 and 2015 selected and reviewed topics related to the areas of commingling waste forms for disposal and deep borehole disposal. In addition to the technical project, interns acquire a broad perspective of the federal agencies involved in managing and disposing of radioactive waste while participating in inter-agency networking opportunities. In this review of the Board internship experience, two past interns discuss the personal impact of the program and how they believe the experience prepared them to face the challenges of a career in management and disposal of spent nuclear fuel and high-level radioactive waste. (authors)

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Recent Advances in Corrosion Science Applicable To Disposal of High-Level Nuclear Waste

High level radioactive waste is accumulating at temporary storage locations around the world and will eventually be placed in deep geological repositories. Many different types of geological formation are under consideration, but all will eventually allow water to contact the metallic waste containers considering that the period of performance required to allow sufficient decay of dangerous radionuclides is on the order of 105 – 106 years. Corrosion of the containers and waste forms in the aqueous repository environment is therefore a concern. This review describes the recent advances of the field of materials corrosion based on the work of the Center for Performance and Design of Nuclear Waste Forms and Containers (WastePD) to address the issues associated with the long-term performance assessment and the design of materials with improved performance, where performance is defined as resistance to aqueous corrosion. Glass, crystalline ceramics, and metals are discussed separately, and then the near field interactions of these different materials classes are addressed. Recommendations for future directions are provided.

Frankel, Gerald↗

Progress on TRANSCEND Theme 1: Integrated Waste Management - 20194

The management of radioactive waste includes mobilisation, processing, packaging, storage, transport and final disposal. Research in the Integrated Waste Management theme of TRANSCEND focuses on underpinning science and engineering in areas of relevance to hazard reduction and decommissioning and the objectives are to: (1) develop new materials for effluent decontamination; (2) demonstrate predictive modelling of sludge/slurry removal, underpinned by experimental data; (3) transform understanding of radiation-driven processes in nuclear waste sludges; and (4) provide underpinning studies to develop innovative processes and wasteform materials. This paper gives overviews of the 16 research projects that will be done over the next 3 years in this theme. (authors)

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NPP SCCs Based Deregulation Process Application Case Design with Internal Block Diagram of SysML - 19237

- It will be possible to group the radioactive wastes from the perspectives on Systems, Structures and Components (SSCs). This paper covers systematic approaches for deregulating grouped decommissioning wastes. SSCs decomposition structure, mass flow of decommissioning waste, sequence and storage time estimation method for deregulation, and interrelationship between them are presented. The expected benefit is the ability possibly to apply deregulation process to SSCs because SSCs breakdown structure is connected with mass flow of decommissioning waste, deregulation option, and storage time. This allows for the application of deregulation strategies and processes on SSCs basis and can enhance the rationale and traceability of the waste grouping. The sequence for deregulation reflects the logic of ensuring that radioactive nuclides meet self-disposal criteria and storing or disposing radioactive wastes if not met. (authors)

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Comparing Legacy Waste Management to Advanced Reactor Waste Management

The Nuclear Energy Agency (NEA) and Natural Resources Canada (NRCan) are organizing an international workshop on the implementation of radioactive waste management and decommissioning strategies in small modular reactors (SMRs) and advance reactor technologies. The event will take place in Ottawa, Canada on 7-10 November 2022. The workshop will convene participants from various fields of expertise in the areas of radioactive waste management, decommissioning, nuclear science and development, transportation, as well as young professionals, communication experts and researchers. The goal of the workshop is to devise a guideline document that will serve implementers in understanding key issues in decommissioning and waste management of new reactors from the design perspective, aiding in the licensing process and in future decommissioning and waste management activities. DOE has invested considerably in the innovation of advanced reactors. Interaction in this workshop allows INL and DOE to articulate the importance of looking at the back-end of the fuel cycle for advanced reactors. The back-end of the fuel cycle is important to the success of advanced reactors, and DOE may need to manage this material in the future after it is discharged from reactors. I have been asked to present at the track titled "Operational and Design Optimization Consideration Related to Decommissioning and Radioactive Waste Management for SMRs/Advanced Reactors".

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Nevada National Security Site Environmental Report Summary 2016

This document is a summary of the full 2016 Nevada National Security Site Environmental Report (NNSSER) prepared by the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/ NFO). This summary provides an abbreviated and more readable version of the full NNSSER. NNSA/NFO prepares the NNSSER to provide the public an understanding of the environmental monitoring and compliance activities that are conducted on the Nevada National Security Site (NNSS) to protect the public and the environment from radiation hazards and from potential nonradiological impacts. It is a comprehensive report of environmental activities performed at the NNSS and offsite facilities over the previous calendar year. The NNSS is currently the nation’s unique site for ongoing national security–related missions and high-risk operations. The NNSS is located about 65 miles northwest of Las Vegas. The approximately 1,360-square-mile site is one of the largest restricted access areas in the United States. It is surrounded by federal installations with strictly controlled access as well as by lands that are open to public entry. In 2016, National Security Technologies, LLC (NSTec), was the NNSS Management and Operations Contractor accountable for ensuring work was performed in compliance with environmental regulations. NNSS activities in 2016 continued to be diverse, with the primary goal to ensure that the existing U.S. stockpile of nuclear weapons remains safe and reliable. Other activities included weapons of mass destruction first responder training; the controlled release of hazardous material at the Nonproliferation Test and Evaluation Complex (NPTEC); remediation of legacy contamination sites; characterization of waste destined for the Waste Isolation Pilot Plant in Carlsbad, New Mexico, or the Idaho National Laboratory in Idaho Falls, Idaho; disposal of low-level and mixed low-level radioactive waste; and environmental research. Facilities and centers that support the National Security/Defense mission include the U1a Facility, Big Explosives Experimental Facility (BEEF), Device Assembly Facility (DAF), National Criticality Experiments Research Center (NCERC) located in the DAF, Joint Actinide Shock Physics Experimental Research (JASPER) Facility, Dense Plasma Focus (DPF) Facility located in the Los Alamos Technical Facility (LATF), and the Radiological/ Nuclear Countermeasures Test and Evaluation Complex (RNCTEC). Facilities that support the Environmental Management mission include the Area 5 Radioactive Waste Management Complex (RWMC) and the Area 3 Radioactive Waste Management Site (RWMS), which has been in cold standby since 2006.

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