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Validation of numerical simulations of activation by neutron flux - 15038

The knowledge of the radionuclide content of radioactive waste is of utmost importance for safety and waste management reasons. Numerical simulations are used at EDF-CIDEN to anticipate the dismantling and the radioactive waste management. The activation scheme by neutron flux developed at EDF-CIDEN comprises four steps. First of all, a 3 dimensional description of the reactor, the chemical composition of each structure, and the neutron sources at nominal power rating conditions are used as the input data to simulate the neutron propagation and to generate a 3 dimensional multi energy group neutron flux distribution in nominal power rating conditions. Secondly, this output data is used with the chemical compositions (including impurities) and the history of the operating conditions to calculate the radiological inventory for each structure. Thirdly, according to the radioactive inventory of each component or sub-component, a waste classification can be made; the classification criteria are based on the levels of radioactivity and radiotoxicity of 143 radionuclides. Finally, comparisons between the calculated radioactive inventories and the results of radio-chemical analyses can be made. These comparisons are made with regards to the activation of 'standard' chemical elements (meaning radionuclides being perfectly modeled with no uncertainty about the chemical concentrations). The results, linked with 'standard' chemical elements, can be used to validate the calculation scheme, including the neutron propagation, the neutron activation and all the other associated simplified assumptions (geometry, history of irradiation, etc). For steel, activation of 'Fe' is retained, and for stainless steel, activation of 'Fe' 'Ni' are retained. Overall, the feedback from Chooz A (Pressurized Water Reactor) shows that numerical simulations produce a slight overestimation of 'Fe-55' and 'Ni-63'. The results linked with minor chemical elements or impurities allowed us to validate the use of the average measured compositions. (authors)

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A Decade of Innovative Approaches to Treating and Dispositioning Radioactive Waste at the Savannah River Site - 20620

This year marks the 70. anniversary of the U.S. Department of Energy's (DOE) Savannah River Site (SRS), located near Aiken, South Carolina. SRS is a key industrial complex responsible for environmental stewardship, environmental cleanup, waste management, and disposition of nuclear materials. SRS also continues to have a role in critical defense-related activities and the reprocessing of used reactor fuel. The SRS encompasses 803 square kilometers (310 square miles) in parts of Aiken, Barnwell, and Allendale counties. The Liquid Waste Mission starts with the safe receipt and storage of radioactive liquid waste in the waste tanks, which principally includes Cold War legacy waste, but also waste from support of National Aeronautics Space Administration missions, medical isotope production, and research activities. This 133,000 cubic meters (m{sup 3}) (35 million gallons [Mgal]) of high-level radioactive waste (HLW) is currently held in 43 large underground waste tanks. The capacity of each of these tanks range from 2,800 m{sup 3} to 5,000 m{sup 3} (0.75 to 1.33 Mgal) and were placed in operation between 1954 and 1986. In July 2009, the DOE awarded a stand-alone contract to execute the Liquid Waste Mission at SRS. The Liquid Waste Contractor selected was Savannah River Remediation LLC1 (SRR), which is responsible for receipt, storage, retrieval and treatment of all HLW, disposal of the decontaminated low-activity waste fraction, as well as operationally closing cleaned HLW tanks. Since July 2009, SRR has successfully grouted and operationally closed six large underground tanks, poured 1,476 canisters of vitrified HLW (a stable glass waste form), treated approximately 34,200 m{sup 3} (9.0 Mgal) of HLW, and dispositioned over 41,200 m{sup 3} (10.9 Mgal) of decontaminated salt solution as low-level waste (LLW) into the Saltstone Disposal Units (SDUs) being constructed by SRR on site. The innovative work performed by SRR in the LLW portion of its mission has earned it the Richard S. Hodes Award. The work conducted by SRR is the same work championed by the late Richard S. Hodes, a respected physician, statesmen, and Chairman of the Southeast Compact Commission for Low-Level Radioactive Waste Management. (authors)

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Environmental issues elimination through circular economy

Environmental efforts of European Union are currently going towards circular economy. Tools like Extended Producer Responsibility and Eco-design were established. The circular economy deals with resources availability issue on one hand and waste management on the other hand. There are few pioneering companies all over the world with some kind of circular economy practice. Generally the concept is not very wide-spread. The paper aims to evaluate possibility of transition towards circular economy in Slovak industrial companies. They need to have an active approach to material treatment of their products after usage stage. Innovation is another important pre-condition for the transition. Main problem of current cradle to grave system is landfilling of valuable materials after one cycle of usage. Their potential value for next manufacturing cycles is lost. Companies may do not see connection between waste management and material resource prices and volatility of supplies. Municipalities are responsible for municipal waste collection and treatment in Slovakia. The circular economy operates by cradle to cradle principle. Company manages material flow until the material comes back to the beginning of manufacturing process by itself or by another partners. Stable material supplies with quite low costs are provided this way. It is necessary to deal with environmental problems in phase of product design. Questionnaire survey results show on one hand low involvement of industrial companies in waste management area, however on the other hand they are open to environmental innovations in future.

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Hydrogen Production from Polyethylene Pyrolysis

Hydrogen is anticipated to play a pivotal role in the future of clean energy and decarbonization efforts, serving as an energy storage medium, a power generation source, and a clean fuel for transportation. While most hydrogen is produced from carbonaceous fossil feedstocks like natural gas, petroleum, and coal, there is growing interest in using refuse-derived fuels such as waste plastics and municipal solid waste (MSW) as alternative feedstocks. Thermochemical processes such as pyrolysis and catalytic cracking can convert nonrecyclable plastics and organic MSW components to produce hydrogen with lower life cycle greenhouse gas emissions when coupled with CO 2 capture. Such approaches not only address waste-management challenges but also reduce methane emissions from landfills. Furthermore, waste feedstocks are low cost and can support meeting demands for hydrogen across various industries. In this work we examined production of hydrogen from high-density polyethylene (HDPE) as a model polymer using pyrolysis. Analytical studies of pyrolysis utilizing gas chromatography–mass spectrometry (GC/MS) provide insights into conversion pathways for plastic waste, potentially reducing the environmental footprint of traditional hydrogen production methods. This work generates a baseline methodology for hydrogen production from plastic pyrolysis with and without a catalyst and the necessary product distribution baseline from key single plastics. The effect of pyrolysis temperature on the conversion of HDPE was evaluated both with and without a catalyst(s), and the product distributions measured via GC/MS were identified and hydrogen formation was quantified. These results will help guide future research efforts to optimize catalysts and processes for more efficient hydrogen production and mixed plastic waste management.

Catalysts↗

Karlsruhe Database for Radioactive Wastes (KADABRA) - Accounting and Management System for Radioactive Waste Treatment - 12275

The data management system KADABRA was designed according to the purposes of the Cen-tral Decontamination Department (HDB) of the Wiederaufarbeitungsanlage Karlsruhe Rueckbau- und Entsorgungs-GmbH (WAK GmbH), which is specialized in the treatment and conditioning of radioactive waste. The layout considers the major treatment processes of the HDB as well as regulatory and legal requirements. KADABRA is designed as an SAG ADABAS application on IBM system Z mainframe. The main function of the system is the data management of all processes related to treatment, transfer and storage of radioactive material within HDB. KADABRA records the relevant data concerning radioactive residues, interim products and waste products as well as the production parameters relevant for final disposal. Analytical data from the laboratory and non destructive assay systems, that describe the chemical and radiological properties of residues, production batches, interim products as well as final waste products, can be linked to the respective dataset for documentation and declaration. The system enables the operator to trace the radioactive material through processing and storage. Information on the actual sta-tus of the material as well as radiological data and storage position can be gained immediately on request. A variety of programs accessed to the database allow the generation of individual reports on periodic or special request. KADABRA offers a high security standard and is constantly adapted to the recent requirements of the organization. (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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Panel Session 12: Featured Country Canada - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects

This panel will share insights from those directly involved in the dialogue among members of the Canadian public, elected officials of host communities, indigenous groups, project proponents, and the Canadian regulator. History has shown time and again that the early and meaningful engagement of stakeholders must go hand-in-hand with technical solutions in order to assure the successful start and finish of waste management and decommissioning projects. In this panel discussion, the requirements for consultation and communication, the tools and strategies used, the results of efforts to date, and plans will be addressed by those at the center of some of Canada's biggest and most controversial radioactive waste projects. Presentations proposed include: 1 - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects (Candida Cianci, Canadian Nuclear Safety Commission (Canada)); 2 - Indigenous Engagement (Bob Watts, Nuclear Waste Management Organization (Canada)); 3 - Engaging the Public and Indigenous Groups Related to Canadian Waste and D and D Projects (Patrick Quinn, Canadian Nuclear Laboratories (Canada)); 4 - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects Canadian Association of Nuclear Host Communities Point of View (Blair Skinner, Local Government District of Pinawa, Manitoba (Canada))

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Optimised management of orphan wastes in the UK

Orphan wastes have properties preventing them from being managed according to existing or currently planned management routes, or lack characterisation so that their management is uncertain. The identification of new management opportunities for orphan wastes could realise significant benefits by reducing the number of processing facilities required, reducing waste volumes, reducing hazard or leading to the development of centres of excellence for the processing of certain types of orphan wastes. Information on the characteristics of orphan waste existing at nuclear licensed sites across the UK has been collated and a database developed to act as a repository for the information gathered. The database provides a capability to analyse the data and to explore possible treatment technologies for each orphan waste type. Thirty five distinct orphan waste types have been defined and possible treatment options considered. Treatment technologies (including chemical, high temperature, immobilisation and physical technologies) that could be applied to one or more of the generic orphan waste streams have been identified. Wiring diagrams have been used to highlight the waste treatment / lifecycle management options that are available for each of the generic orphan groups as well as identifying areas for further research and development. This work has identified the potential for optimising the management of orphan wastes in a number of areas, and many potential opportunities were identified. Such opportunities could be investigated by waste managers at waste producing nuclear sites, to facilitate the development of new management routes for orphan wastes. (authors)

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Economic and environmental optimization of waste treatment

Highlights: • Optimizing waste treatment by incorporating LCA methodology. • Applying different objectives (minimizing costs or GHG emissions). • Prioritizing multiple objectives given different weights. • Optimum depends on objective and assumed displaced electricity production. - Abstract: This article presents the new systems engineering optimization model, OptiWaste, which incorporates a life cycle assessment (LCA) methodology and captures important characteristics of waste management systems. As part of the optimization, the model identifies the most attractive waste management options. The model renders it possible to apply different optimization objectives such as minimizing costs or greenhouse gas emissions or to prioritize several objectives given different weights. A simple illustrative case is analysed, covering alternative treatments of one tonne of residual household waste: incineration of the full amount or sorting out organic waste for biogas production for either combined heat and power generation or as fuel in vehicles. The case study illustrates that the optimal solution depends on the objective and assumptions regarding the background system – illustrated with different assumptions regarding displaced electricity production. The article shows that it is feasible to combine LCA methodology with optimization. Furthermore, it highlights the need for including the integrated waste and energy system into the model.

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Positive Social License Solicitation and Affiliation Development through Non-Traditional Engagement Vectors - 19423

Generally speaking, the nuclear industry is very effective at accepting the positive and educated merits of 'all things nuclear,' including rationales for nuclear power supply, fuel, and waste-related considerations. However, the general public on average tends to be invariably wary of the nuclear industry, especially when it comes to waste management considerations, and furthermore, is greatly swayed by public sentiment and influences that suggest that 'nuclear is ominous.' This stance is especially true when it comes to waste management. This paper is based on the premise that traditional engagement and social license solicitation initiatives are at best, marginally effective at influencing the favorability within public opinion. However, there is tremendous opportunity and untapped potential to engage in a more meaningful and effective manner, by adopting a more holistic and fundamental approach to social engagement and public influence. This paper elaborates on this approach by presenting sustainable, effective strategies for practical methods of non-traditional social engagement to introduce, expose, educate, inform, develop, and influence a non-biased appreciation for nuclear industry considerations. Starting from a belief that early exposure and awareness of the nuclear industry through indirect engagement manifests a non-threatening, positive affinity for the subject matter, a sustained, deliberate, and multi-vector engagement campaign is effective at establishing a pro-nuclear disposition. Additionally, rather than relying on a few established and known (and perhaps perceived as biased) advocacy entities, this paper establishes a methodology of mobilizing a varied and wide range of indirect stakeholders to disseminate and manifest the desired-and unbiased-message. In effect, rather than coming from a position where traditional industry advocacy sources vie and lobby for disseminating the merits and realities of the industry, this strategy establishes a means to have non-biased, non-nuclear agents 'tell the story' about the nuclear industry. Practical examples will be provided detailing how some of the proposed methodologies have been successfully deployed. This includes hosting a province- (state)-wide technical competition for 100+ elementary school children, using the context and narrative of a spent-fuel removal and storage-handling system. This specific experience resulted from introducing complex nuclear concepts and environments in a very accessible manner to the young students, while also capitalizing on the curiosity of the their parents, teachers, friends, and community in an open and engaging information and awareness initiative that they would not have otherwise encountered through the traditional engagement vectors. With continued similar experiences, this cohort will become part of the desired voting demographic faced with questions and decisions around nuclear power, waste handling, and storage. Drawing upon their early engagement and deliberate exposure to the subject matter, over time, this audience will invariably result in a much more engaged, educated, informed, and positively-inclined demographic. In summary, a positive shift in the prevailing general public sentiment can be achieved through a a broad, long-term, and wide-reaching early engagement strategy. (authors)

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Remote Collection of Radioactive Waste at Chalk River Laboratories - 19425

Remote handling of radioactive waste may be required during a variety of decommissioning and waste management activities. Based on the level of radiation and complexity of the application, the design, development and implementation of novel electromechanical systems can offer optimal solutions. At Canadian Nuclear Laboratories, current decommissioning and waste management projects routinely employ solutions including innovative and unique tools, test rigs, mock-ups, robotics, unmanned aerial vehicles, and automated systems. CNL ability to integrate an experienced team from a wide range of technical areas make such solutions possible. In this paper, we present an example of remotely controlled systems to collect highly radioactive waste materials from storage tanks at the Chalk River Laboratories. (authors)

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New approaches for MOX multi-recycling

Due to its low fissile content after irradiation, Pu from used MOX fuel is considered by some as not recyclable in LWR (Light Water Reactors). The point of this paper is hence to go back to those statements and provide a new analysis based on AREVA extended experience in the fields of fissile and fertile material management and optimized waste management. This is done using the current US fuel inventory as a case study. MOX Multi-recycling in LWRs is a closed cycle scenario where U and Pu management through reprocessing and recycling leads to a significant reduction of the used assemblies to be stored. The recycling of Pu in MOX fuel is moreover a way to maintain the self-protection of the Pu-bearing assemblies. With this scenario, Pu content is also reduced repetitively via a multi-recycling of MOX in LWRs. Simultaneously, {sup 238}Pu content decreases. All along this scenario, HLW (High-Level Radioactive Waste) vitrified canisters are produced and planned for deep geological disposal. Contrary to used fuel, HLW vitrified canisters do not contain proliferation materials. Moreover, the reprocessing of used fuel limits the space needed on current interim storage. With MOX multi-recycling in LWR, Pu isotopy needs to be managed carefully all along the scenario. The early introduction of a limited number of SFRs (Sodium Fast Reactors) can therefore be a real asset for the overall system. A few SFRs would be enough to improve the Pu isotopy from used LWR MOX fuel and provide a Pu-isotopy that could be mixed back with multi-recycled Pu from LWRs, hence increasing the Pu multi-recycling potential in LWRs.

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Geological Disposal Concept Selection Aligned with a Voluntarism Process - 13538

The UK's Radioactive Waste Management Directorate (RWMD) is currently at a generic stage in its implementation programme. The UK site selection process is a voluntarist process and, as yet, no communities have decided to participate. RWMD has set out a process to describe how a geological disposal concept would be selected for the range of higher activity wastes in the UK inventory, including major steps and decision making points, aligned with the stages of the UK site selection process. A platform of information is being developed on geological disposal concepts at various stages of implementation internationally and, in order to build on international experience, RWMD is developing its approach to technology transfer. The UK has a range of different types of higher activity wastes with different characteristics; therefore a range of geological disposal concepts may be needed. In addition to identifying key aspects for considering the compatibility of different engineered barrier systems for different types of waste, RWMD is developing a methodology to determine minimum separation distances between disposal modules in a co-located geological disposal facility. RWMD's approach to geological disposal concept selection is intended to be flexible, recognising the long term nature of the project. RWMD is also committed to keeping alternative radioactive waste management options under review; an approach has been developed and periodic reviews of alternative options will be published. (authors)

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Port Granby Project Overview - 13208

The Port Granby Project is an integral part of the Port Hope Area Initiative (PHAI), and is located approximately 14 kilometres west of the Municipality of Port Hope in the adjacent Municipality of Clarington, Ontario. The principal objective of the project is the excavation and relocation of low-level radioactive waste (LLRW) and marginally contaminated soils, which were deposited at the Port Granby Waste Management Facility (PGWMF) by Eldorado Nuclear Limited during the period 1955 to 1988, to a new, highly engineered above-ground Long-term Waste Management Facility (LTWMF) to be constructed on a nearby site. The Environmental Assessment for the Project was approved in 2009 August and the required Waste Nuclear Substance License was received in 2011 November. Once the detailed engineering design was completed, in 2011 March, the Port Granby Project was divided into three major contracts for construction implementation purposes. The first of these contracts was completed in late 2012 and the second is planned to start in early 2013. The contracting process for the third major contract is also expected to be completed during 2013. This paper provides an overview of the Port Granby Project as well as discussion on the status of the Project, including the regulatory approvals process, the approach to contracting the construction works and an update of work recently completed and soon to get underway. (authors)

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The perspective awareness model - Eliciting multiple perspectives to formulate high quality decisions

A great deal of attention is given to the importance of communication in environmental remediation and radioactive waste management. However, very little attention is given to eliciting multiple perspectives so as to formulate high quality decisions. Plans that are based on a limited number of perspectives tend to be narrowly focused whereas those that are based on a wide variety of perspectives tend to be comprehensive, higher quality, and more apt to be put into application. In addition, existing methods of dialogue have built-in limitations in that they typically draw from the predominant thinking patterns which focus in some areas but ignore others. This can result in clarity but a lack of comprehensiveness. This paper presents a Perspective Awareness Model which helps groups such as partnering teams, interagency teams, steering committees, and working groups elicit a wide net of perspectives and viewpoints. The paper begins by describing five factors that makes cooperation among such groups challenging. Next, a Perspective Awareness Model that makes it possible to manage these five factors is presented. The two primary components of this model --- the eight 'Thinking Directions' and the 'Shared Documentation' --- are described in detail. Several examples are given to illustrate how the Perspective Awareness Model can be used to elicit multiple perspectives to formulate high quality decisions in the area of environmental remediation and radioactive waste management. (authors)

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Perspectives on Previous DOE Transportation Acquisition Efforts - 19049

The Department of Energy (DOE) is planning for future large-scale transport of commercial Spent Nuclear Fuel (SNF) and High-Level Radioactive Waste (HLW) to eventual disposal and/or storage facilities. Various options for procuring transportation services are being evaluated. To inform this work, a review of past comments received on DOE transportation acquisition activities in the early 1990's through 2016 was conducted. Through the course of data collection, staff analyzed comments submitted from ten DOE initiatives from DoE's Office of Civilian Radioactive Waste Management (OCRWM) and DoE's Office of Nuclear Energy (DOE-NE). This paper summarizes and outlines key themes arising from these comments. Past issues identified by a wide variety of commenters (nuclear industry and cask vendors, nuclear utilities and purchasers, states, Tribes, local governments, rail carriers, nongovernmental organizations, trade organizations, engineering firms, and members of the public) were examined. These issues concerned DoE's activities to make maximum use of the private sector to transport and store SNF and HLW. The key themes analyzed include: Uniqueness of the Shipping Campaign, Views on Privatization, Industry Risk and Privatization, Unclear Roles and Responsibilities, and Responsibilities Recommended for DOE to Maintain. This paper concludes by discussing lessons that can be learned from analyzing these public comments and what that may mean moving forward in the U.S. radioactive waste management program. (authors)

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FY2019 Performance Assessment Annual Review for the E-Area Low-Level Waste Facility

The Savannah River Site (SRS) E-Area Low-Level Waste Facility (ELLWF) consists of six types of disposal units described in the Performance Assessment (PA) (WSRC, 2008): Low Activity Waste Vault (LAWV), Intermediate Level Vault (ILV), Trenches [Slit Trenches (STs), Engineered Trenches (ETs), and Component-in-Grout (CIG) Trenches], and Naval Reactor Component Disposal Areas (NRCDAs). The ELLWF is a part of the Solid Waste Management Facility (SWMF). SWMF is managed and operated by the SRS Management and Operations prime contractor, Savannah River Nuclear Solutions (SRNS). Within SRNS, the Solid Waste Management (SWM) organization is responsible for operating the SWMF, and the Savannah River National Laboratory (SRNL) is the technical agency responsible for preparing and maintaining the PA. SWMF operations have been performed at SRS since 1952. The mission of the SWMF is to provide storage, processing, disposal, and shipment of radioactive, hazardous, and mixed waste. The SWMF is committed to treat, store, and dispose of these waste products in a manner that protects the environment and the health and safety of the facility worker, the co-located worker, and the offsite general public. Wastes handled in the SWMF include low level waste, transuranic waste, hazardous waste, Toxic Substances Control Act waste, and mixed waste (containing both hazardous and radioactive constituents).

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Sociological survey in a municipality with a high level separate collection programme in an area of historic unpopularity

Highlights: • Behaviours, opinions and knowledge of citizens on MSW management were investigated. • The knowledge level was better than that of nearby university students and citizens. • The higher the education level, the greater the level of knowledge was. • The local authority showed a leading role in terms of waste management. • Trust is the key to any social program success including waste management programs. - Abstract: Behaviours, opinions and knowledge of citizens on MSW and separate collection were investigated in the city of Mercato San Severino (about 22,000 people), in the Campania region of Southern Italy that is an area suffering from a serious solid waste emergency that has lasted over 17 years due to the absence of treatment facilities. The image of heaps of rubbish in the streets of Naples and other nearby cities is only one side of the coin. Mercato San Severino has adopted an effective kerbside collection system since 2001 and a pay-as-you-throw program during 2005, guaranteeing more than the minimum level of recycling required by the Italian legislation. Structured questionnaires were administered to a sample of 500 people in 2010. Chi-square tests of independence were applied to state whether the differences were statistically significant (5%). About 90% of the sample stated that the success of the separate collection program was due to either the citizens and local authority or only the local authority, highlighting the leading role of the local authority and confirming that trust is the key to any social program success. The registered level of knowledge was better than that of nearby university students and citizens. The higher the education level, the greater the level of knowledge was.

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