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Methods of capturing and immobilizing radioactive nuclei with metal fluorite-based inorganic materials

Methods of capturing and immobilizing radioactive nuclei with metal fluorite-based inorganic materials are described. For example, a method of capturing and immobilizing radioactive nuclei includes flowing a gas stream through an exhaust apparatus. The exhaust apparatus includes a metal fluorite-based inorganic material. The gas stream includes a radioactive species. The radioactive species is removed from the gas stream by adsorbing the radioactive species to the metal fluorite-based inorganic material of the exhaust apparatus.

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UNREVIEWED DISPOSAL QUESTION EVALUATION: Disposal of the Perma-Fix Environmental Services Macroencapsulated Debris at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This Unreviewed Disposal Question Evaluation (UDQE) assesses whether the Perma-Fix Environmental Services (PERM) Macroencapsulated Debris, Radioactive Lead (Pb) Solids, Cadmium/Mercury/Silver (Cd/Hg/Ag) Containing Batteries from U.S. Department of Energy (DOE) Generators (PERM000000027, Revision 28 [PERM 2021]) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). Disposal of the PERM Macroencapsulated Debris, Radioactive Pb Solids, Cd/Hg/Ag Containing Batteries from DOE Generators meets all performance objectives of DOE Manual DOE M 435.1-1, Radioactive Waste Management Manual, Chapter IV, Section P (DOE 1999). The PERM Macroencapsulated Debris, Radioactive Pb Solids, Cd/Hg/Ag Containing Batteries from DOE Generators stream is recommended for acceptance without conditions.

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Second Quarter Transportation Report - Fiscal Year 2021 - Waste Shipments to and from the Nevada National Security Site, Radioactive Waste Management Complex

This report satisfies the U.S. Department of Energy (DOE) commitment to prepare a quarterly summary of waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) in Area 5. This report summarizes the second quarter of fiscal year (FY) 2021 and serves as a quarterly report for the following types of shipments: Low-Level Radioactive Waste (LLW) Mixed Low-Level Radioactive Waste (MLLW) Classified Non-Radioactive (CNR) Waste Classified Non-Radioactive Hazardous (CNRH) Waste

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Performance and safety assessment of the co-location of the near surface radioactive waste disposal facilities and borehole disposal concept in the Philippines

The Philippine Nuclear Research Institute (PNRI) in collaboration with the interagency technical committee on radioactive waste has been undertaking a national project to find a final solution to the country's low to intermediate level radioactive waste. The strategy adopted was to co-locate 2 disposal concepts that will address the types of radioactive waste generated from the use of radioactive materials. This strategy is expected to compensate for the small volumes of waste generated in the Philippines as compared to countries with big nuclear energy programs. It will also take advantage of the benefits of a shared infrastructure and R and D work that accompany such project. The preferred site selected from previous site selection and investigations is underlain by highly fractured 'andesitic volcaniclastics' mantled by residual clayey soil which act as the aquifer or water bearing layer. Results of investigation show that the groundwater in the area is relatively dilute and acidic. Springs at the lower elevations of the footprint also indicate acidic waters. The relatively acidic water is attributed to the formation of sulfuric acid by the oxidation of the pyrite in the andesite. A preliminary post closure safety assessment was carried out using the GMS MODFLOW and HYDRUS softwares purchased through the International Atomic Energy Agency (IAEA) technical assistance. Results from MODFLOW modeling show that the radionuclide transport follows the natural gradient from the top of the hill down to the natural discharge zones. The vault dispersion model shows a circular direction from the vaults towards the faults and eventually to the creeks. The contaminant transport from borehole shows at least one confined plume from the borehole towards the creek designated as Repo1 and eventually follows downstream. The influx of surface water and rainfall to the disposal vault was modeled using the HYDRUS software. The pressure head and water content at the base of the foundation layer and the bottom of the concrete is where a significant reduction in water content can be observed. It is also noted that water content and pressure remain constant after one year. (authors)

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3rd Quarter Transportation Report FY2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments.

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Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

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Management of Ir-192 Disused Sealed Sources with Long-Lived Radioactive Contaminants

Iridium-192 sealed sources are the most widely used sealed source in industrial applications in Brazil. They are not recyclable and in the end of the useful life, they are discarded as radioactive waste. The recommended management strategy of this waste is decay in storage and disposal as exempt waste because the half-life is only 73.8 days. Presently, thousands of Ir- 192 sources are under storage waiting release. Surprisingly, sources that were under storage for more than ten years and for which no measurable contact dose rate was expected still present significant remaining radioactivity. The examination of the gamma spectra of these sources showed the presence of Co-60 and the gamma emission lines from the Ir-192m2 isomer, the metastable isotope with half-life of 241 years, which is also formed by the irradiation of natural iridium. The aim of the study reported in this paper is to characterize the Ir-192 disused sources under interim storage at the Radioactive Waste Management Department, considering the presence of minor contaminants in the irradiated iridium and the fraction of the total initial activity of the sources that is attributable to that metastable isotope. The radioactive inventories at the end of the irradiation and after the decay period were predicted using the Scale 6.0 code and the results were compared with activity measurements of the disused sources by gamma spectrometry. (authors)

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Can we use Pictograms in a Long Term Communication System Related to a Radioactive Waste Repository? - 18301

Pictograms are often mentioned as a possible tool for sending messages about radioactive waste repositories in a far future, when the understand ability of our languages will have been lost. But they have also limits, related to the use of conventions that may fade over time. The goals of a signaling system for the long term may be (1) to alert (raise attention), (2) to inform of an underlying danger due to the existence of radioactive wastes, (3) to induce a favorable behavior (provoke or deter actions) in order not to disturb the performance of the repository. The quest for trans-cultural and trans-generational performance requires that some universal semiotic features be identified, shared by human beings of various cultures nowadays, and from far in the past to the present. Considering the typology of colors in various languages, the use of colors in ancient rock art and in children's drawings, a dedicated role may be assigned to each of the three colors, white, black and red/ocher, with a high potential for sustainable meaning: 1) red background = pay attention to this object because of the simple presence of the red color, that is to say the first color felt as color; 2) white inscription = absence of the object / action represented; 3) black inscription = presence of the object / action represented. The representation of a human body in movement inside a context is also understandable by people from various cultures. The combination of these 'semiotic primitives', used as relevant semantic features of the object and/or the experience to be represented, and 'topo-sensitive' criteria, used for pictogram production processes, would thus become a way to conceive a trans-cultural and trans-generational sign system for the signaling of radioactive danger. The choice of the stone could guarantee the durability of the support; the color could guarantee its visibility; and both could guarantee the transmission of the message. Combining these criteria could open the way to a long term communication system about radioactive waste repositories. (authors)

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A step-by-step development of radioactive waste management strategy

Fennovoima is Finland's third nuclear power company founded in 2007. Fennovoima will build a new nuclear power plant, Hanhikivi 1, in Pyhajoki municipality located in Northern Finland. Currently Fennovoima is evaluating bids from reactor suppliers. Originally two suppliers, AREVA and Toshiba Heavy Industries were invited to bid for the plant but later also a bid from Rosatom were invited. The plant supplier will be selected in 2013. Platom is a Finnish company with extensive experience in radioactive waste management. In the beginning of 2008, Platom was assigned by Fennovoima as radioactive waste management consultant and to develop radioactive waste management strategy and to support Fennovoima in negotiations with plant suppliers in waste management aspects. Since Fennovoima has started, there have been some changes to the regulatory requirements which had to be taken into account while developing the strategy. One important change is due to the Government Degree 27.11.2008/736 which establishes a new waste category of very low-level waste following international development and the 'new' IAEA waste classification. Other important change was introduced by the change 342/2008 to the Nuclear Energy Act allowing some nuclear waste to be delivered to another country for treatment. These and many more requirements had to be considered when developing the strategy. Early work by Platom was mostly done to support development of application for Decision-in-Principle. This was the first important licensing step for Fennovoima. Work started with studies and plans which were used by Fennovoima to gather the know-how required to draw up the application. Descriptions of waste streams and waste management technologies were developed as well as preliminary waste inventories and studies for final disposal, including preliminary dimensioning of the repository facilities. Based on these plans nuclear regulator's preliminary safety assessment was performed. The work was successfully completed as in 2010 the Government of Finland granted Fennovoima a permit to build a new nuclear power plant. The work continued in 2012 when bids were received for EPR and ABWR type reactors. Plans developed earlier were elaborated into a detailed strategy and the proposed waste management solutions were evaluated. This allowed feedback from the bids into the strategy and to the bid specification and they both were developed. Also waste inventories were elaborated which allowed development of reactor design specific disposal strategies. The main objective of work has been to establish basis for safe and efficient radioactive waste management which meets all the relevant national and international recommendations, requirements and regulations, takes advantage of best available and state-of-art technologies and offers fit-for-purpose solutions. All the work was performed to accommodate requirement based management system. (authors)

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4th Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. There was one shipment of two drums sent for offsite treatment and disposal. This report summarizes the 4th quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014.

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Radioactive Waste Management in Non-Nuclear Countries - 13070

This paper challenges internationally accepted concepts of dissemination of responsibilities between all stakeholders involved in national radioactive waste management infrastructure in the countries without nuclear power program. Mainly it concerns countries classified as class A and potentially B countries according to International Atomic Energy Agency. It will be shown that in such countries long term sustainability of national radioactive waste management infrastructure is very sensitive issue that can be addressed by involving regulatory body in more active way in the infrastructure. In that way countries can mitigate possible consequences on the very sensitive open market of radioactive waste management services, comprised mainly of radioactive waste generators, operators of end-life management facilities and regulatory body. (authors)

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Conditioning and Repackaging of Spent Radioactive Cs-137 and Co-60 Sealed Sources in Egypt - 13490

Radioactive Sealed sources (RSSs) are widely use all over the world in medicine, agriculture, industry, research, etc. The accidental misuse and exposure to RSSs has caused significant environmental contamination, serious injuries and many deaths. The high specific activity of the materials in many RSSs means that the spread of as little as microgram quantities can generate significant risk to human health and inhibit the use of buildings and land. Conditioning of such sources is a must to protect humans and environment from the hazard of ionizing radiation and contamination. Conditioning is also increase the security of these sources by decreasing the probability of stolen and/or use in terrorist attacks. According to the law No.7/2010, Egyptian atomic energy authority represented in the hot laboratories and waste management center (centralized waste facility, HLWMC) has the responsibility of collecting, conditioning, storing and management of all types of radioactive waste from all Egyptian territory including spent radioactive sealed sources (SRSSs). This paper explains the conditioning procedures for two of the most common SRSSs, Cs{sup 137} and Co{sup 60} sources which make up more than 90% of the total spent radioactive sealed sources stored in our centralized waste facility as one of the major activities of hot laboratories and waste management center. Conditioning has to meet three main objectives, be acceptable for storage, enable their safe transport, and comply with disposal requirements. (authors)

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Development of Approach for Long-Term Management of Disused Sealed Radioactive Sources - 13630

Radioactive sources are used widely throughout the world in a variety of medical, industrial, research and military applications. When such radioactive sources are no longer used and are not intended to be used for the practice for which an authorization was granted, they are designated as 'disused sources'. Whether appropriate controls are in place during the useful life of a source or not, the end of this useful life is often a turning point after which it is more difficult to ensure the safety and security of the source over time. For various reasons, many disused sources cannot be returned to the manufacturer or the supplier for reuse or recycling. When these attempts fail, disused sources should be declared as radioactive waste and should be managed as such, in compliance with relevant international legal instruments and safety standards. However, disposal remains an unresolved issue in many counties, due to in part to limited public acceptance, insufficient funding, and a lack of practical examples of strategies for determining suitable disposal options. As a result, disused sources are often stored indefinitely at the facilities where they were once used. In order to prevent disused sources from becoming orphan sources, each country must develop and implement a comprehensive waste management strategy that includes disposal of disused sources. The International Atomic Energy Agency (IAEA) fosters international cooperation between countries and encourages the development of a harmonized 'cradle to grave' approach to managing sources consistent with international legal instruments, IAEA safety standards, and international good practices. This 'cradle to grave' approach requires the development of a national policy and implementing strategy, an adequate legal and regulatory framework, and adequate resources and infrastructure that cover the entire life cycle, from production and use of radioactive sources to disposal. (authors)

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Revised Arrangements for the Management of Solid and Non-Aqueous Radioactive Waste - 12452

In 2010, Atomic Weapons Establishment (AWE) identified a requirement to implement revised management arrangements for the generation, storage and disposal of radioactive waste. A thorough review of the current arrangements/processes was undertaken which included both legal compliance requirements and the identification of business improvement opportunities. On completion of this review a suitable project team was established and in 2011 an integrated Radioactive Waste Management process was implemented throughout the business. Initial results have shown measurable improvements within Radioactive Waste management compliance, operator understanding and increased business efficiency. Through the development and implementation of the revised working arrangements AWE has been able to continue to demonstrate both legal compliance to its regulators along with business efficiency and effectiveness improvements. Simple to follow process maps have improved employees understanding of Radioactive Waste management requirements, provided them with easily accessible information and ensured the business operates in a single coherent manner. The implementation of a modern electronic data management system has ensured all waste related information is easily retrievable and appropriately maintained. The additional functions that have been built into the system have reduced the potential for human error and increased the overall efficiency of the Waste Management department through the use of the automated report generation functionality. (authors)

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Prospects and Challenges in the Management of Non-Retrievable Radioactive Waste in the Russian Federation - 17212

In 2011, the Federal Law 'On the Management of Radioactive Waste' was enacted in the Russian Federation setting a framework for the Unified State System for Radioactive Waste Management and establishing a mandatory requirement for safe radioactive waste (RW) disposal. Particular category of 'non-retrievable RW' was defined given the amount of RW generated by that time, the issues associated with relevant sites, as well as the experience gained during the implementation of nuclear legacy programs. It was specified that in situ disposal is the preferred management option for this category of waste rather than RW retrieval and re-disposal due to relevant radiation and financial aspects. In 2011 - 2015, a set of high-priority tasks on taking the inventory of accumulated RW was accomplished. This work also provided for demonstrating the feasibility and making key decisions on the final stages on their lifecycle and relevant end-state strategies. Facilities holding non-retrievable RW were divided into two categories: - subject to transition into near-surface storage facilities by constructing additional safety barriers; - subject to controlled long-term storage followed by remediation. Efforts on a number of surface liquid RW storage water reservoirs falling under the first category launched back in the 20. century were completed. The new federal program provides for a set of follow-up efforts to be completed at 12 facilities. As it comes to the second category, the main task was to develop a set of safety management options, as well as some computational methods to demonstrate the feasibility of the selected end-state strategies. The most considerable efforts were made at the Techa Cascade of water reservoirs being the largest liquid radioactive waste (LRW) storage facility in the world that holds over 360 million m{sup 3} of waste with uncertain legal status, the lack of relevant computational models to predict its state. The paper summarizes the data on defining the end states of non-retrievable RW, completed and scheduled efforts on implementing relevant long-term safety strategies. The paper focuses on subsurface repositories and near-surface LRW storage reservoirs considered as common types of facilities holding non-retrievable RW. (authors)

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Testing and Starting up of the Plasma Melting Facility for Industrial Treatment of Radioactive Waste - 17362

The operation and maintenance of nuclear power plants, the nuclear fuel cycle in general, research laboratories and pharmaceutical, medical and industrial facilities generate low-level radioactive waste which, along with the historical radioactive waste from past nuclear activities, needs to be treated and stored, awaiting final disposal. Plasma technology offers a very effective way of treating this waste with a high volume reduction factor (VRF), free from organics, liquids and moisture, and meets without a doubt the acceptance criteria for safe storage and disposal. By means of a plasma beam of approximately 5000 deg. C, the inorganic materials are melted into a glassy slag, containing most of the radioactive isotopes while the organic material is gasified and afterwards oxidized in an afterburner and purified in an off-gas cleaning system. This paper describes the principles of plasma, the different waste feed systems, off-gas treatment and operational experience and future plasma plants. More specifically, it presents the new full-scale plasma facility for the treatment of radioactive waste at the Kozloduy Nuclear Power Plant in Bulgaria for which construction and assembly was finalized end of August 2016. It also describes in more detail the Site Acceptance Tests (SAT) of this facility. This facility is designed and built as an EPC contract by the Joint Venture Iberdrola Ingenieria y Construccion (Spain) and Belgoprocess (Belgium). (authors)

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Recent Developments in Radioactive Waste Management in the Federal Republic of Germany - 17450

In 2013 the Federal Parliament and the Federal Council passed the Act Concerning the Search and Selection of a Site for a Repository for Heat-Generating Radioactive Waste and the Amendment of Other Acts (Site Selection Act). It was a restart for the search for a repository for especially heat-generating waste in Germany. As a first step in May 2014 the Commission 'Storage of High-Level Radioactive Waste' started their work. Their aim was to debate and clarify the principle questions concerning the management of heat-generating radioactive waste. As well as to evaluate and determine the fundamentals for the Site Selection Process e.g. safety requirements, exclusion criteria, minimum requirements and consideration criteria for the site selection. They also evaluated the organizational and procedural arrangements in the scope of waste management. As a first act to implement the suggestions of this Commission the organizational structures in waste management were greatly altered. This reorganization not only had a significant influence on the waste management of high-active, but also on the management of low- and intermediate-active waste management in the Federal Republic of Germany. In 2015 a second Commission started its work focusing on the funding of waste management in Germany. The results of this Commission were presented in April 2016. At the moment the suggestions of this Commission are being implemented, changing the financial responsibilities for waste management in the Federal Republic of Germany. The presentation will focus on changes and the developments of radioactive waste management in Germany and talk about the ongoing process in implementing the suggestions of the two Commissions. (authors)

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OECD NEA radioactive waste repository metadata management (RepMet) initiative (2014-2018) - 15614

The OECD/NEA Radioactive Waste Repository Metadata Management (RepMet) initiative aims to bring about a better understanding of the identification and administration of metadata - a key aspect of data management - to support national programmes in managing their radioactive waste repository data, information and records in a way that is both harmonised internationally and suitable for long-term management and use. At this point in the project, the main focus lies on 'waste packages at their storage sites ready for geological disposal' but excluding spent fuel and high level waste (HLW). Later work will deal with metadata collected on spent fuel and HLW as well as with different phases of repository development: design and construction, and operation. In order to develop metadata, RepMet members have provided lists of data items they currently collect and manage for packaged waste. The lists, albeit it non comprehensive, suggest that the number and type of data items varies importantly from organisation to organisation. At term, RepMet plans to generate a comprehensive list of such data items and their metadata. In parallel, RepMet is developing a document which examines a selected number of existing metadata standards. Because of the specialist nature of radioactive waste management, including waste processing facilities, disposal facilities and waste packages, existing metadata standards do not seem to be transferable as defined. Rather, RepMet will explore such standards to identify relevant principles for possible adaptation to the radioactive waste management community. (authors)

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