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At least 829 records · Page 46
All sourcesNASA NTRSDOE OSTI
DOE OSTI2020

Lessons Learned in the Development of Industry Guidance - 20279

The availability of industry guidance on different aspects of waste management forms a valuable reference for waste practitioners. The guidance typically details the principles, processes and practices that should be consulted during each stage of the relevant activities. It also includes relevant regulatory and international requirements, appropriate case studies and examples of best practices to illustrate technical concepts and make the information available to the reader in an accessible manner. Over recent years Wood have developed (or are developing) a number of industry guidance documents on a range of topics including Solid Waste Characterization, Routine Water Quality Monitoring on Nuclear Sites: Pipeline Characterization: Determining Background Radioactivity for Land Quality Assessment: Interim Storage and Aqueous Waste Management. This talk provides an overview of lessons learned along the way including: - the importance of stakeholder engagement through the process: - how to identify 'good practice'; - the importance of iterative development; and - the selection of illustrative and informative case studies. (authors)

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DOE OSTI2015

Improvement of the management of residual waste in areas without thermal treatment facilities: A life cycle analysis of an Italian management district

Highlights: • LCA analysis of two option for residual waste management. • Exploitation of mechanical physical sorting facility for extracting recyclable from RMSW. • Processing the mechanically sorted organic fraction in bioreactor landfill. • Sensitivity analysis demonstrate high influence for impact assessment of substitution ratio for recycle materials. - Abstract: Starting from an existing waste management district without thermal treatment facilities, two different management scenarios for residual waste were compared by life cycle assessment (LCA). The adoption of a bioreactor landfill for managing the mechanically sorted organic fraction instead of bio-stabilization led to reduction of global warming and fresh water eutrophication by 50% and 10%, respectively. Extraction of recyclables from residual waste led to avoided emissions for particulate matter, acidification and resource depletion impact categories. Marginal energy and the amount of energy recovered from landfill gas marginally affected the LCA results. On the contrary the quality of the recyclables extracted can significantly modify the eco profile of the management schemes.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Establishment of Master Plans on Spent Nuclear Fuel in Korea - 17097

This study pertains to the Master Plans for High-Level Radioactive Waste Management prepared by the Korean Government on the basis of the predicted amount of spent nuclear fuel in Korea and the results of public discussion of the issue. The Korean Government has established the Master Plans for High-Level Radioactive Waste Management on the basis of the results of public discussion of the issue to secure the safety of the nationals and resolve the policy uncertainty that has been accumulated for more than 30 years. To provide a legal basis for the implementation of the Master Plans, legislation of the Act on High-Level Radioactive Waste Management Procedures (tentative) will be promoted, and an independent implementation institute, (tentatively named as) the Management Facility Strategy Committee, and an administrative supporting organization, the Planning and Promotion Group, will be organized and operated. This study is expected to transfer experience of and lessons from determining national policy to countries that have not established their final management policy for spent fuel, based on the formation of national consensus. (authors)

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DOE OSTI2020

TRU Outdoor Operations

This detailed operating procedure (DOP) documents the process for handling, staging, and distributing (i.e., packing/unpacking) transuranic (TRU) waste in compliance with P409, LANL Waste Management, TA55-RD-539, TA-55 FOD Waste Management Requirements, and P409-1, LANL Waste Acceptance Criteria., at designated outdoor storage and operations locations at LANL TA-55.

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DOE OSTI2018

Spectrally Selective Mirrors with Combined Optical and Thermal Benefit for Photovoltaic Module Thermal Management

Waste heat generated during daytime operation of a solar module will raise its temperature and reduce cell efficiency. In addition to thermalization and carrier recombination, one major source of excess heat in modules is the parasitic absorption of light with sub-bandgap energy. Parasitic absorption can be prevented if sub-bandgap radiation is reflected away from the module. We report on the design considerations and projected changes to module energy yield for photonic reflectors capable of reflecting a portion of sub-bandgap radiation while maintaining or improving transmission of light with energy greater than the semiconductor bandgap. Using a previously developed, self-consistent opto-electro-thermal finite-element simulation, we calculate the total additional energy generated by a module, including various photonic reflectors, and decompose these benefits into thermal and optical effects. We show that the greatest total energy yield improvement comes from photonic mirrors designed for the outside of the glass, but that mirrors placed between the glass and the encapsulant can have significant thermal benefit. We then show that optimal photonic mirror design requires consideration of all angles of incidence, despite unequal amounts of radiation arriving at each angle. We find that optimized photonic mirrors will be omnidirectional in the sense that they have beneficial performance, regardless of the angle of incidence of radiation. By fulfilling these criteria, photonic mirrors can be used at different geographic locations or different tilt angles than their original optimization conditions with only marginal changes in performance. We show designs that improve energy output in Golden, Colorado by 3.7% over a full year. This work demonstrates the importance of considering real-world irradiance and weather conditions when designing optical structures for solar applications.

14 SOLAR ENERGY↗
DOE OSTI2024

Consolidated Interim Storage Advantages and Disadvantages from Prior Reports and Studies

The question of whether centralized storage of civilian spent nuclear fuel (SNF) should be part of the federal waste management system as an intermediate step before permanent disposal has been debated for more than four decades. Since the Nuclear Waste Policy Act (NWPA) (U.S. House of Representatives 1982) was enacted, the need for interim storage facilities (ISFs) as part of the federal waste management system has been analyzed and documented in numerous reports and studies. This paper summarizes the advantages and disadvantages as described in those reports of incorporating an ISF into the waste management system.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2023

Consolidated Interim Storage Advantages and Disadvantages from Prior Reports and Studies

The question of whether centralized storage of civilian spent nuclear fuel (SNF) should be part of the federal waste management system as an intermediate step before permanent disposal has been debated for more than four decades. Since the Nuclear Waste Policy Act (NWPA) [1] was enacted, the need for interim storage facilities (ISFs) as part of the federal waste management system has been analyzed and documented in numerous reports and studies. This presentation summarizes the advantages and disadvantages, as described in those reports, of incorporating an ISF into the waste management system.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2012

Formulating a VET roadmap for the waste and recycling sector: A case study from Queensland, Australia

Highlights: Black-Right-Pointing-Pointer Existing qualifications do not meet the needs of the sector in Queensland. Black-Right-Pointing-Pointer Businesses may not be best positioned to identify training needs. Black-Right-Pointing-Pointer Companies are developing training internally to meet their own specific needs. Black-Right-Pointing-Pointer Smaller companies lack the resources to develop internal training are disadvantaged. Black-Right-Pointing-Pointer There is industry support for an entry-level, minimum industry qualification. - Abstract: Vocational Education and Training (VET) is an essential tool for providing waste management and recycling workers with the necessary skills and knowledge needed to beneficially influence their own employment and career development; and to also ensure productivity and safe working conditions within the organisations in which they are employed. Current training opportunities within Queensland for the sector are limited and not widely communicated or marketed; with other States, particularly Victoria and New South Wales, realising higher numbers of VET enrollments for waste management courses. This paper presents current VET opportunities and trends for the Queensland waste management sector. Results from a facilitated workshop to identify workforce requirements and future training needs organised by the Waste Contractors and Recyclers Association of Queensland (WCRAQ) are also presented and discussion follows on the future training needs of the industry within Queensland.

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DOE OSTI2013

Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

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DOE OSTI2015

Decommissioning concepts for the norwegian nuclear research facilities Halden and Kjeller - 15022

The Norwegian nuclear research facilities Halden and Kjeller are near the end of their current operational licenses. Thus, the Norwegian Ministry of Trade, Industry and Fisheries have decided that a concept evaluation study shall be made on the decommissioning alternatives for these facilities. This task was given to Ndcon (Westinghouse and Studsvik) with their broad experience in decommissioning planning and decades of nuclear expertise, together with DNV GL, that is certified in Norway for concept evaluation studies. The decommissioning alternatives that have been evaluated are strategy, end-state and waste management options. The decommissioning strategies are the IAEA defined immediate dismantling, deferred dismantling and entombment. The different end-states that have been evaluated are unrestricted use (green field), light industry (brown field) and other nuclear activity, in which the site will continue to have a nuclear license even after the decommissioning. The waste management options are direct disposal of materials, recycling of materials off-site and recycling on-site. The result of the cost estimation is that it is possible to identify viable alternatives for a chosen decommissioning strategy, end state and waste management options. The expected duration of the decommissioning program is 10 years for both sites, the dismantling and demolition period is expected to be able to perform within 4 years. (authors)

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DOE OSTI2013

Training activities at FSUE 'RADON' and Lomonosov's Moscow state university under practical arrangements with IAEA

The International Education Training Centre (IETC) at Moscow Federal State Unitary Enterprise (FSUE) 'Radon', in co-operation with the International Atomic Energy Agency (IAEA), has developed expertise and provided training to waste management personnel for the last 15 years. Since 1997, the educational system of the enterprise with the support of the IAEA has acquired an international character: more than 470 experts from 35 countries - IAEA Member States completed the professional development. Training is conducted at various thematic courses or fellowships for individual programs and seminars on IAEA technical projects. In June 2008 a direct agreement (Practical Arrangements) has been signed between FSUE 'Radon' and the IAEA on cooperation in the field of development of new technologies, expert's advice to IAEA Member States, and, in particular, the training of personnel in the field of radioactive waste management (RWM), which opens up new perspectives for fruitful cooperation of industry professionals. A similar agreement - Practical Arrangements - has been signed between Lomonosov's MSU and the IAEA in 2012. In October 2012 a new IAEA two-weeks training course started at Lomonosov's MSU and FSUE 'Radon' in the framework of the Practical Agreements signed. Pre-disposal management of waste was the main topic of the courses. The paper summarizes the current experience of the FSUE 'Radon' in the organization and implementation of the IAEA sponsored training and others events and outlines some of strategic educational elements, which IETC will continue to pursue in the coming years. (authors)

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DOE OSTI2020

Panel Session 99: Commercial LLW Management: Global Perspective

This panel focused on opportunities and challenges in providing commercial nuclear waste management services in a global context. The panelists commented on their approach to establishing new businesses, overcoming communication barriers acquiring / maintaining skills and capabilities and delivering commercial nuclear waste management projects in a range of regulatory and socio-economic environments. The panel discussion was followed by a Q and A session with audience participation. Panelist with presentations: BGE Technology (Thilo von Berlepsch)

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DOE OSTI2015

Chooz-A steam generators characterization - 15205

EDF nuclear waste management requires a deep understanding of characterization, classification and waste sorting operations. In fact, French nuclear waste management defines several classes with specific management, treatment and storage facilities. Based on particular criteria, the more the radiological risk of the nuclear waste is important, the more its management will be complex and expensive. During the dismantling of the first French pressurized reactor Chooz-A, decontamination of the primary water circuits (not including the reactor vessel), the steam generators and the pressurizer have been carried out in order to reduce their activity levels. Thanks to these decontamination operations, and a specific characterization methodology, EDF was able to de-classify the 4 steam generators and store them in one piece at the ANDRA Very Low Level Activity disposal facilities instead of the Low and Intermediate Level activity one. This de-classification allowed EDF to avoid important cutting and packaging processes. Therefore, significant dose reductions for the operators and financial gain have been made. To characterize and declare Chooz-A SG activity, EDF-CIDEN uses a methodology defined by the French institute of atomic energy, CEA. The method is based on external gamma spectrometry measurements performed with NaI collimated detectors, associated with MERCURAD simulations providing the transfer functions for the detectors and activity sources. Internal measurements are carried out with a CZT (CdZnTe) probe inside the SG tubes to refine the 3D model. In fact, the primary side represents the main source of activity, and understanding its contamination distribution is important to reduce the model and calculation uncertainties. Measurements eventually provide SG {sup 60}Co global activity, from which the activities of other radionuclides of the spectrum are determined using scaling factors. The final activity declaration takes into account the standard deviation of the measurements in order to cover the uncertainties of the methodology. Thereby, the declaration is 'slightly over-estimative', enough to meet the waste storage facility acceptance criteria. (authors)

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DOE OSTI2019

Managing Knowledge Over Time for Supporting Radioactive Waste Geological Disposal Project Development - 19028

Projects designed to define, build, operate and monitor radioactive waste disposal solutions require the transmission of knowledge over several decades and the preservation of memory over several centuries. This is particularly acute for the geological disposal project 'Cigeo' led by the French national radioactive waste management agency (Andra) as far as the requirements in terms of reversibility lead to the choice of an incremental design that allows to integrate learning resulting from continuous improvement of knowledge. For instance, for robustness purposes, Cigeo is designed on the basis of currently proven technologies, but its step-by-step construction in successive stages must make it possible to integrate improvements derived from the scientific and technical progress as well as from experience feedback from its exploitation. In the field of industrial activity, a significant proportion of the knowledge and skills implemented by employees of a company are not known or even identified by the human resources organization or the mid-management staff. This is mainly due to the fact that (i) the organized knowledge-sharing is often based on documentary tools but little on social modalities and (ii) the organization of knowledge is mostly cross-cutting to the managerial lines. To overcome this bias, a global and integrated approach to knowledge management is currently the focus of Andra's specific efforts. Cross-disciplinary groups and close intergenerational links positioned throughout the life of the projects aim specifically at continuous and participative knowledge sharing, capitalization and transmission. Then, devices aiming at systematic dissemination of and access to knowledge support experience feedback and provide unified collaboration, traceability and decision-support at all scales. (authors)

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DOE OSTI2013

The involvement of SCK-CEN in decommissioning projects

SCK-CEN is the Belgian Nuclear Research Centre. Founded in the mid-fifties, it has accumulated experience and know-how in all fields of the nuclear power production: in the neutronics calculation, radiation protection, waste management, fuel performance and analysis, nuclear measurements, radiochemistry, reactor technology, etc. Since 1989, SCK-CEN has launched Decommissioning activities to deal with the Technical Liabilities created by 40 years of operation. The main projects started were: - the dismantling of the BR3 PWR reactor; - the dismantling of active laboratories and the decontamination of buildings for unrestricted reuse; - the management of the waste arising from the refurbishment activities of the BR2, especially the management of the high active beryllium matrix. In 1989, the BR3 reactor, a Pressurized Water Reactor, was selected by the European Commission as one of the four pilot dismantling projects in the framework of the EC five year RTD program on dismantling nuclear installations. Through this project, SCK-CEN has built up a broad know-how in dismantling and decommissioning operations. This know how concerns the decontamination for dose rate reduction and/or free release of materials, tele-operated techniques for cutting highly activated components of a reactor, concrete decontamination techniques, characterization techniques of radioactive waste or for free release of components and development of decommissioning management and record-keeping of material streams and of nuclear material accountancy. SCK-CEN is now actively involved in other decommissioning projects in Belgium and in expertise abroad. After giving an overview of the main achievements and the perspectives of the decommissioning of the BR3 reactor, the paper intends to present the involvement of SCK-CEN in the other decommissioning projects and to give an overview of our activities and capacities. (authors)

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DOE OSTI2013

Vitrification of IFR and MSBR halide salt reprocessing wastes

Both of the genuinely sustainable (breeder) nuclear fuel cycles (IFR - Integral Fast Reactor - and MSBR - Molten Salt Breeder Reactor -) studied by the USA's national laboratories would generate high level reprocessing waste (HLRW) streams consisting of a relatively small amount ( about 4 mole %) of fission product halide (chloride or fluoride) salts in a matrix comprised primarily (about 95 mole %) of non radioactive alkali metal halide salts. Because leach resistant glasses cannot accommodate much of any of the halides, most of the treatment scenarios previously envisioned for such HLRW have assumed a monolithic waste form comprised of a synthetic analog of an insoluble crystalline halide mineral. In practice, this translates to making a 'substituted' sodalite ('Ceramic Waste Form') of the IFR's chloride salt-based wastes and fluoroapatite of the MSBR's fluoride salt-based wastes. This paper discusses my experimental studies of an alternative waste management scenario for both fuel cycles that would separate/recycle the waste's halide and immobilize everything else in iron phosphate (Fe-P) glass. It will describe both how the work was done and what its results indicate about how a treatment process for both of those wastes should be implemented (fluoride and chloride behave differently). In either case, this scenario's primary advantages include much higher waste loadings, much lower overall cost, and the generation of a product (glass) that is more consistent with current waste management practices. (author)

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DOE OSTI2015

Integrating decontamination strategies into a waste estimation support tool for radiological incidents - 15284

In the planning and preparedness stages for a response to a radiological incident, it is important to include waste management considerations when developing the decontamination/demolition/cleanup approach because waste management can be a driver for time and cost. An individualized type of strategy based on the occupancy of affected buildings may be an effective approach. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a novel application of the Federal Emergency Management Agency (FEMA) Hazus-MH software. WEST enables users to estimate the characteristics, amount, and residual radioactivity of waste generated from remediation and cleanup activities after a radiological incident, including incidents caused by radiological dispersal devices and improvised nuclear devices, as well as nuclear power plant accidents. This paper will describe the recently released update to WEST, which includes the ability to export the waste estimate results back into ArcGIS for further visualization. (authors)

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DOE OSTI2026

Analysis of NuCycle® Process Waste Streams and Identification of Candidate Waste Forms (CRADA 719) Abstract

The objective of this project is to support collaboration between PNNL and Curio to address technical gaps in the immobilization of waste streams generated by the NuCycle® process, thereby improving the overall viability of the technology. This work will be carried out in two phases, described below. Phase 1 – Waste Management Study The first phase consists of a comprehensive waste management study focused on the waste streams produced during the NuCycle® process, including those containing long lived fission products (LLFPs, e.g., I 129) and transuranic elements (TRUs). This phase involves compiling waste compositions and characteristics based on recently completed NuCycle® testing and modeling efforts. Established waste forms and processing methods will be identified for streams where they are applicable.

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