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Artykuły w czasopismach na temat "Nuclear Waste Technical Review Board"
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Cantlon, John E. "Nuclear waste management in the US: The Nuclear Waste Technical Review Board's perspective". Nuclear Engineering and Design 176, nr 1-2 (listopad 1997): 111–20. http://dx.doi.org/10.1016/s0029-5493(96)01339-8.
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Fernández-Arias, Pablo, Diego Vergara i Álvaro Antón-Sancho. "Global Review of International Nuclear Waste Management". Energies 16, nr 17 (27.08.2023): 6215. http://dx.doi.org/10.3390/en16176215.
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In the current situation of global energy transition, nuclear energy maintains its reputation as a stable power generation technology, without dependence on other resources and without CO2 emissions. However, one of the main problems with its use is the management of the radioactive waste it generates, which has given rise to different international strategies: (i) reprocessing; (ii) storage; and (iii) disposal. Given the interest generated by nuclear energy in recent times and the need to manage the waste generated, this paper presents a global review of the different international nuclear waste management strategies, using a scientific method based on (i) a bibliometric review of the scientific publications related to nuclear waste management and (ii) an analysis of the technical aspects of the different international management strategies. The effective and safe management of nuclear waste will contribute to the advancement of international nuclear energy development strategies that encourage the construction of new nuclear power plants and the lifetime extension of existing ones.
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Fayek, Mostafa, i Julie Brown. "Natural and Anthropogenic Analogues for High-Level Nuclear Waste Disposal Repositories: A Review". Canadian Mineralogist 59, nr 1 (1.01.2021): 287–317. http://dx.doi.org/10.3749/canmin.2000051.
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ABSTRACT Projects involving deep geological disposal of nuclear waste are unique in that predictive models of long-term safety often involve geological timeframes. This manuscript provides a review of natural and anthropogenic analogues for high-level nuclear waste disposal in a deep geological repository. We also occasionally highlight analogues that have been used for low- and intermediate-level waste. Most studies define natural analogues as either naturally occurring or anthropogenic systems. In this paper, we distinguish between natural analogues and anthropogenic analogues because the latter generally provide non-technical (anecdotal) illustrations of concepts and processes for the safety case, whereas the former can provide technical and quantitative information. In addition, natural analogues can provide information over geological time scales (millions of years) and spatial scales (kilometers), whereas anthropogenic analogues provide information over a much more limited time scale (hundreds or thousands of years). Regardless of the definition, analogue studies provide one of the multiple lines of evidence intended to increase confidence in the safe geological disposal of high-level nuclear waste. They are deemed necessary because they complement the experiments that are carried out over a period of months or years. They also provide a way to validate numerical long-term safety assessment models with information and data covering geological time scales and spatial scales. The first part of this review describes the analogue concept. The second and third parts provide examples of natural and anthropogenic analogues for engineered barrier systems and natural barriers. Part four describes analogues for complex coupled transport processes. Finally, we discuss general and specific areas of future research. A concerted effort should be made to ensure that there is a transfer of data from the complex, natural analogue field studies to simplistic models which, by necessity, are used to evaluate the long-term safety of deep geological repositories. Field analogue studies should be planned to interface with laboratory experiments and, ultimately, with in situ field experiments, when the final repository site is selected. This will involve using natural analogue data in a quantitative way to support the deep geological repository safety case.
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Durant, Darrin. "Resistance to Nuclear Waste Disposal: Credentialed Experts, Public Opposition and their Shared Lines of Critique". Scientia Canadensis 30, nr 1 (30.06.2009): 1–30. http://dx.doi.org/10.7202/800524ar.
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Abstract This article asks the question whether, in regard to controversial technical decision-making, lay public groups advance different kinds of resistance than credentialed experts. This question is explored via a case-study analysis of one of Canada's major public controversies of the past quarter century—nuclear waste disposal. Having arrived on the policy radar in 1977, nuclear waste remained an internal government/nuclear industry matter until terms of reference for a public inquiry were announced in 1989. Several access points for public input followed that announcement: scoping sessions in 1990, comments received during 1994-96 on an Environmental Impact Statement (EIS) prepared by Atomic Energy Canada Limited (AECL), nation-wide public hearings in 1996-97, and ongoing public consultation since 2002. This article focuses on the comments on the EIS, and discusses several lines of shared resistance: the expert judgment of AECL was disputed, the lack of peer review was criticized, accusations of unreliability were made, and general deficiencies in the EIS were attributed to narrow terms of reference and poor institutional culture. This article recommends the use of a dramaturgical approach to technical texts, and reveals the assumptions framing the dualist notion that one can unambiguously separate technical and social criticisms of technical projects.
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Ramesh Kumar, S., G. Renuka, Sheela Bijlwan, Ahmed H. R. Abbas, Smriti Sharma i K. B. Waghulde. "Nuclear Fusion Reactors: Challenges and Potential as a Future Energy Source". E3S Web of Conferences 540 (2024): 13014. http://dx.doi.org/10.1051/e3sconf/202454013014.
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This review article delves into the promising yet challenging realm of nuclear fusion reactors as a potential future energy source. The paper provides a comprehensive overview of global fusion research, highlighting its potential benefits and the technical obstacles that have hindered its widespread commercial adoption. Fusion energy, with its abundant resources, minimal waste generation, and low emissions, emerges as a long-term solution for a sustainable energy future. However, its technical complexities suggest that its widespread commercialization may not be realized until the end of the century. The article further explores the environmental compatibility, safety, and resource implications of fusion energy. A significant emphasis is placed on the paramount importance of safety in the development of fusion power reactors. The review underscores the need for robust safety cases, accident identification methods, and the establishment of internationally recognized safety standards. Additionally, the paper identifies knowledge gaps and areas necessitating further research, ensuring that fusion power stations meet rigorous safety objectives while minimizing environmental impact. Through a holistic examination of fusion’s potential and challenges, this review offers insights into its role in shaping the future energy landscape.
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Balakhanova, T. V., I. M. Chuiko, E. V. Parusov i E. V. Oliinyk. "Some aspects of the use of steel during out of reactor storage and transportation of spent nuclear fuel. (Review)". Fundamental and applied problems of ferrous metallurgy 37 (2023): 389–406. http://dx.doi.org/10.52150/2522-9117-2023-37-389-406.
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In the world, the nuclear industry is considered an ideal option for an environmentally friendly source of energy generation, based on the separation of the radioactive nuclide of the chemical element 235U. When generating electricity from nuclear power plants, the main disadvantage is the generation of radioactive waste. After spent fuel is removed from a nuclear reactor, it is placed in special containers containing absorption and retention elements. It is obvious that the storage and transportation of spent nuclear fuel plays an important role in the development and overall safety of the nuclear industry, and high-quality neutron-absorbing materials are the basis for the successful manufacture of reliable structures and containers. The development of modern neutron absorption materials ensures reliability, safety, storage duration, as well as reducing the cost of logistics operations associated with the transportation of radioactive waste. Based on the results of the analysis of scientific and technical sources, modern ideas about materials for the manufacture of containers, which are used for storage and transportation of nuclear fuel waste, are summarized. The advantages and disadvantages of the main materials used in the disposal of spent nuclear fuel are considered. It has been established that, from an economic point of view, the most rational material for storing and transporting radioactive waste is ferritic stainless steel with a high boron content, which, in addition to absorption abilities, is characterized by other properties required for this type of product. Since boron has a low ability to dissolve in both austenite and ferrite, this leads to the formation of borides of various types, which contribute to the embrittlement of the structural material. At the same time, the distribution of borides over the volume of a metal product is determined not only by a set of properties, but also by the protective properties of the material, as well as the manufacturability of the final product from it. Despite the fact that boron-containing steels of the ferritic class have been known for a long time, issues related to the processes of structure formation, increasing technological and operational properties still remain insufficiently studied and controversial. There is also no information on the influence of heat treatment on the formation of the structure and mechanical properties of finished products made of ferritic stainless steels. Successful solution of these scientific and technical problems will ensure the production of modern high-quality neutron-absorbing containers for off-reactor storage and transportation of spent nuclear fuel.
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Johnson, Chelsea, Nandini G, Santosh K. Balivada i Surya Prakash. "Radioactive Waste Management in a Medical Cyclotron Facility - A Review". International Journal of Health Technology and Innovation 1, nr 03 (23.12.2022): 20–23. http://dx.doi.org/10.60142/ijhti.v1i03.53.
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The cyclotron is a device used to create radioactive atoms with a short half-life (radioactive isotopes) that can be utilised for research and medical imaging. When nuclear and radiation facilities are utilized, serviced, or decommissioned, radioactive waste is produced. The amount of radioactive waste produced is greatly decreased by good operating procedures. Iodine-123, Technetium-99m, Iodine-131, Gallium-67 Thallium-201 and fluorine-18 fluorodeoxyglucose are among the radionuclides utilised in medicine. The most widely used gaseous/aerosol radionuclides are (aerosolized) technetium-99m, xenon-133, and krypton-81m. The use of radionuclides (radioactive element) for industrial process control and instrumentation, medical diagnostic and therapeutic purposes, as well as numerous uses in research, education, agriculture, geological exploration, construction, and other human endeavors, results in radioactive waste. These applications generate a variety of radioactive waste, which can come from sealed sources and be in solid, liquid, or gaseous form. If the trash containing considerable amounts of radionuclides is not handled properly, there may be serious concerns to both the environment and human health. Due to the wide variety of waste kinds addressed, special consideration must be paid to safety concerns and regulatory management. This article will examine the fundamental procedures for managing radioactive waste in compliance with the regulatory agencies like AERB (Atomic Energy Regulatory Board) and IAEA (International Atomic Energy Agency).
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Ravi, Rajesh, Oumaima Douadi, Manoranjitham Ezhilchandran, Mustapha Faqir, Elhachmi Essadiqi, Merouan Belkasmi i Shivaprasad K. Vijayalakshmi. "A practical approach-based technical review on effective utilization of exhaust waste heat from combustion engines". Energy Sources, Part A: Recovery, Utilization, and Environmental Effects 45, nr 4 (1.08.2023): 10010–33. http://dx.doi.org/10.1080/15567036.2023.2242321.
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Lambert, Timothy, i Xuan Hieu Nghiem. "Review of the Deployment of and Research into Generation III & IV Nuclear Fission Reactors for Power Generation". PAM Review Energy Science & Technology 1 (3.08.2015): 90–108. http://dx.doi.org/10.5130/pamr.v1i0.1387.
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Nuclear fission is one of the more popular and efficient sources of energy that has been used in the last few decades. In the setting of the ongoing worldwide debate of the energy problem, this paper will review the different types and generations of nuclear reactors, and do comparisons with other notable energy sources (biofuel and fusion). The current generations III, III+, IV of reactor (mostly pressurized water reactors), their thermal efficiency, technical (structure and configuration), lifetime, energy output and how the systems contrast are discussed. The paper was written by gathering information from UTS library online database, as well as online articles related to fission power, all sources dating from 2000s onwards. Nuclear fission power is a very dense energy source as it provides higher amount of free energy than other energy sources from the same amount of fuel. The drawback, which is the high amount of radioactive waste that accumulates over time, along with thermal efficiency are improved upon by the current and next generations of reactors.
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Froese, Annika, Zoe Felder i Steffen Drees. "The importance of social science research in nuclear waste management shown by three projects on public participation". Safety of Nuclear Waste Disposal 2 (6.09.2023): 245–46. http://dx.doi.org/10.5194/sand-2-245-2023.
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Abstract. The disposal of nuclear waste is not only a technical challenge but also a sensitive socio-political issue. Especially in Germany, the search for a final repository for highly radioactive waste is complicated by past and present societal conflicts surrounding the use of nuclear energy. Hence, safe nuclear waste management requires social science research that examines the nuclear waste problem in its social context. We illustrate this claim by presenting the results of three contract research projects dealing with public participation, commissioned by Germany's Federal Office for the Safety of Nuclear Waste Management (BASE). Public participation is central to the safety of nuclear waste management. First, the safety of disposal practices is often improved by the general public's critical input. Second, public participation may increase the acceptability of nuclear waste disposal in a particular region, which is important to ensure the successful implementation of waste management strategies. Third, public participation serves to preserve knowledge and maintain competence, since it keeps the topic of nuclear waste present in people's minds. Therefore, social science research that improves public participation measures makes a significant contribution to the safety of nuclear waste management. This contribution presents three projects that illustrate how social science can improve public participation. The first project surveyed the German population regarding the search for a final repository for highly radioactive waste. The second examined the utility of digital participation tools. The third project dealt with the legal, political, and cultural challenges of cross-border public participation. The first project surveyed a representative sample of the German population. Survey participants answered questions pertaining to the structure and current state of Germany's search for a final repository, their main concerns in relation to this search, and their desire to participate in the search. Results show that Germans are most concerned about safety issues and currently have little desire to actively participate in the search, but instead demand to be well informed. The results of this project allow BASE to adapt its public participation strategy to the German population's needs, thereby increasing its effectiveness. The second project examined the utility of digital participation tools in the context of the search for a final repository. Past events implemented by BASE were marked by the underrepresentation of young people, women, and also people with lower educational attainment and migrant backgrounds. First, the project team carried out a literature review that showed that the use of digital tools does not solve issues of underrepresentation. The team then used focus groups to demonstrate the importance of schools, appealing designs, and gamification when addressing young people. The project ended with a workshop wherein experts discussed the project's results and developed prototypes of digital tools to support BASE's efforts to engage young people. Reaching young people is crucial to preserving knowledge and increasing the acceptability of nuclear waste disposal, since today's younger generations will be affected by and responsible for the final repository. The third project dealt with the legal, political, and cultural challenges of implementing public participation across borders. BASE will have to facilitate public participation in multiple countries if the proposed site for the final repository is in close proximity to Germany's border. The project team first conducted a literature review to analyze the challenges of cross-border public participation. The second part consisted of in-depth case studies of three different planning procedures, conducted in Switzerland, Germany, and the Czech Republic. Finally, researchers conducted five regional case studies, covering regions in Denmark, the Netherlands, the Czech Republic and Poland, Austria, and France. The project resulted in a sketch of a model cross-border participation process, ensuring that BASE will be able to successfully implement such a process. These projects show that social science research can improve the quality of public participation measures. Since public participation is crucial to the safety of nuclear waste management, so are the social sciences.
Książki na temat "Nuclear Waste Technical Review Board"
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P, Donnelly J., Kennedy J. E i U.S. Nuclear Regulatory Commission. Division of High-Level Waste Management, red. Peer review for high-level nuclear waste repositories: Generic technical position. Washington, DC: Division of High-Level Nuclear Waste Management, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1988.
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P, Donnelly J., Kennedy J. E i U.S. Nuclear Regulatory Commission. Division of High-Level Waste Management, red. Peer review for high-level nuclear waste repositories: Generic technical position. Washington, DC: Division of High-Level Nuclear Waste Management, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1988.
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American Society of Mechanical Engineers. i Institute for Regulatory Science, red. Spent nuclear fuel canister welding concept: Technical peer review report, report of the review panel. [New York, N.Y.]: ASME International, 2004.
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United States Department of Energy Environmental Management Advisory Board: Public meeting : U.S. Department of Energy, Program Review Center. [Washington, D.C.?: The Dept.], 1995.
Znajdź pełny tekst źródłaStreszczenia konferencji na temat "Nuclear Waste Technical Review Board"
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Bahr, Jean, Steven Becker, Susan L. Brantley, Allen Croff, Efi Foufoula-Georgiou, Tissa Illangasekare, K. Lee Peddicord, Paul Turinsky i Mary Lou Zoback. "MOVING THE U.S. NUCLEAR WASTE PROGRAM FORWARD: SIX OVERARCHING RECOMMENDATIONS FROM THE NUCLEAR WASTE TECHNICAL REVIEW BOARD". W GSA Connects 2021 in Portland, Oregon. Geological Society of America, 2021. http://dx.doi.org/10.1130/abs/2021am-369632.
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Vidaechea, Sergio, i Manuel Ondaro. "The Decommissioning of the CIEMAT Nuclear Research Center". W ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59321.
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CIEMAT, formerly the Nuclear Energy Board (JEN), is the Spanish Centre for Energy-Related, Environmental and Technological Research. Located in Madrid, it used to have more than 60 facilities in operation that allowed a wide range of activities in the nuclear field and in the application of ionising radiations. Particularly significant among these facilities were the research reactors, particle accelerators, hot cells and nuclear fuel manufacturing and processing plants. At present the centre, which is authorised as a single nuclear facility, includes various installations, some of them are now obsolete, shut down and in dismantling phases. In 2000 CIEMAT started the “Integrated plan for the improvement of CIEMAT installations (PIMIC)”, which includes activities for the decontamination, dismantling and rehabilitation of obsolete facilities. This paper will describe the decommissioning process carried out at CIEMAT Research Centre, and will review the key aspects of the project, including site remediation and release.
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Voizard, Patrice, Stefan Mayer i Gerald Ouzounian. "Geological Repository for Nuclear High Level Waste in France From Feasibility to Design Within a Legal Framework". W The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7034.
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Over the past 15 years, the French program on deep geologic disposal of high level and long-lived radioactive waste has benefited from a clear legal framework as the result of the December 30, 1991 French Waste Act. To fulfil its obligations stipulated in this law, Andra has submitted the “Dossier 2005 Argile” (clay) and “Dossier 2005 Granite” to the French Government. The first of those reports presents a concept for the underground disposal of nuclear waste at a specific clay site and focuses on a feasibility study. Knowledge of the host rock characteristics is based on the investigations carried out at the Meuse/Haute Marne Underground Research Laboratory. The repository concept addresses various issues, the most important of which relates to the large amount of waste, the clay host rock and the reversibility requirement. This phase has ended upon review and evaluation of the “Dossier 2005” made by different organisations including the National Review Board, the National Safety Authority and the NEA International Review Team. By passing the “new”, June 28, 2006 Planning Act on the sustainable management of radioactive materials and waste, the French parliament has further defined a clear legal framework for future work. This June 28 Planning Act thus sets a schedule and defines the objectives for the next phase of repository design in requesting the submission of a construction authorization application by 2015. The law calls for the repository program to be in a position to commission disposal installations by 2025.
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Berton, Marie-Anne, Julian Cruickshank, Catherine Ollivier-Dehaye, Horst Monken-Fernandes i Peter Orr. "Progress With Nuclear Energy Agency Task Group on Nuclear Site Restoration". W ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96265.
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The Nuclear Energy Agency (NEA) Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking of a limited number of organisations, mainly from NEA member countries. The objective of the CPD is to acquire and share information from operational experience in decommissioning nuclear installations that is useful for future projects. The information exchange includes biannual meetings of the Technical Advisory Group (TAG) and supporting projects on topics. The TAG has decided to form a Task Group to review nuclear site restoration starting in March 2012 that involves nuclear operators, experts and regulators. The group is supported by the International Atomic Energy Agency (IAEA) that is leading similar work on legacy sites. Within NEA Counties, several nuclear sites are being restored for beneficial reuse. Restoration is normally considered the last activity in a sequence of decommissioning steps but increasingly the value of long-term planning and parallel remediation is being recognised. It is essential that regulators know that liabilities are well understood (well characterised) and there is adequate financial provision to carry on the remediation works. Operators are also learning that early intervention is needed to ensure prevention and minimisation of leaks and spills of radioactive and non-radioactive contaminants in order to reduce groundwater and soil contamination, thus reducing overall liabilities and ensuring protection of the environment. Early intervention needs to be guided by good practices that include adequate site characterisation, reliable conceptual models and defined goals. Currently most nuclear site restoration work takes place at the legacy nuclear sites. This work has emphasised the need for better clarity in terms of the regulatory expectations for site restoration. At other nuclear sites the drivers are less evident and there is a risk that land quality issues are overlooked. The aim of the Task Group is to share information on experiences, approaches and techniques for land quality management at selected nuclear sites to ensure risks to workers and the environment, costs and disruption to decommissioning programmes are minimised. The project will also highlight the successes and lessons to learn from experience of remediation that will be helpful to operational situations on nuclear sites. The paper will report on progress with analysis of national and site level questionnaires and early consideration of case studies. The questionnaires will provide a snapshot of the current status, issues and best practice with site restoration and the case studies will provide in depth illustrations of practice with nuclear site or remediation projects.
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Masuda, Yusuke, Yukihiro Iguchi, Satoru Kawasaki i Masami Kato. "Status of the Support Researches for the Regulation of Nuclear Facilities Decommissioning in Japan". W ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40245.
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In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the “Prioritized Nuclear Safety Research Plan (August 2009)” of the Nuclear Safety Commission of Japan and the situation of operators faculties, “Regulatory Support Research Plan between FY 2010–2014” was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3, measuring method, release procedure and analysis code for the site release were studied for the establishment of the license termination process in the future. From FY 2010, based on the new plan, we have started the researches for the standardization of review process of decommissioning plan for power reactors and nuclear fuel cycle facilities, establishing the process and criteria of license termination and appropriate method of management of decommissioning waste based on the waste form confirmation process.
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Nam, Y. S., Y. H. Kim, K. L. Jeon, S. K. Lee, K. S. Choi i C. S. Cho. "Structural Intergrity Evaluation Approach for PWR Spent Nuclear Fuel". W ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40176.
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PWR fuel assembly (FA) experiences many changes from the time it is manufactured, loaded in the reactor and removed from the reactor for reprocessing or stroage etc. Any of these alterations which impact spent nuclear fuel (SNF) integrity should be considered to design a cask/canister. Regarding the cask/canister design, there could be a freedom to design a system that mitigates the forces transmitted to SNF and fuel rods. If the cask/canister design prevents or mitigates forces transmitted to its contents such that structural integrity is not significantly compromised, the detailed SNF properties are necessary to make a decision of the elaborated design parameters. An approach to those work formations is to analyze mechanical characteristics of structural components. Those informations are also used to evaluate hypothetical accident, to select limiting FA for cask/canister to accommodate various kinds of SNFs and to design transportation/storage system for SNFs. Especially, FA structural properties are a sort of essential data. Thus, in this paper, some approaches to evaluate SNF mechanical characteristics are suggested through the existing technical information review, some test data and the analysis methodology, and also closely study the mechanical characteristics of a representative SNF for its general comprehension.
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Brickner, Robert H. "Behind the Scenes: Sneak Peak at Procurement of Innovative Recycling and Waste-to-Fuel Conversion System Expected to Yield 80% Diversion". W 19th Annual North American Waste-to-Energy Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/nawtec19-5456.
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New Hanover County, NC, hired Gershman, Brickner & Bratton, Inc. (GBB) to help prepare a Request for Proposals (RFP) for the management and long-term operations of the County’s solid waste disposal facilities, which include a secure landfill with more than 40 years of remaining life, a 20+ year old waste-to-energy (WTE) plant, and seven recycling drop-off sites receiving over 200,000 tons per year. The RFP requested a single-service provider to provide all of the services currently being undertaken by the County under a single contract going forward. During the course of the procurement, GBB’s Project Manager made three presentations to the New Hanover County Board of Commissioners (County Board), advancing the RFP process from eight vendor proposals, to interviews of five firms and performing a technical and economic review of each, to short-listing two firms, to the final recommendation of going forward with high-tech start-up R3 Environmental LLC (R3). In September 2010, the County Board signed a landmark contract with R3 for the management of the County’s waste system that was intended to position the County as a world leader in innovative disposal, according to County officials. Under the agreement, R3 was to implement a modern Municipal Solid Waste (MSW) processing facility pulling out recyclables and making a low-ash, high-BTU Refused-Derived Fuel (RDF) biomass product, refurbishing the current mass-burn WTE facility into an RDF biomass-fired system, and implementing a new construction waste and demolition debris recycling (C&D) processing system. The new solid waste sorting facility, with advanced machinery, dubbed a “Smart MRF,” was expected to be in operation in two years, extracting recyclables and converting the organic waste stream into fuel. R3 guaranteed to divert over 80% of the incoming solid waste from the landfill. This paper provides a unique behind-the-scenes look at the procurement process used to select this “innovative technology proposal” from R3 as it pertained to recycling potential, carbon credits and renewable energy credits, and significant long-term cost benefits to the County. It will also provide a review of the vendor evaluation process that led to this landmark contract, from the RFP preparation, proposals evaluation, technical/economic reviews, short-listing, recommendations, and technical contract negotiation.
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Gilli, Ludivine. "Engaging Local Stakeholders on Technical Issues: Test Case at the La Hague Reprocessing Plant". W ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59211.
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In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) lead a pilot action dealing with the decommissioning of a workshop located on the site of Areva’s La Hague fuel-reprocessing plant site in Northwestern France. The purpose of the pilot program was to test ways for IRSN and a few local stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the local stakeholders to review the operator’s decommissioning application and provide input. The pilot program confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues. Three factors influence the extent of the challenge: the knowledge gap between experts and local stakeholders, the conflict between transparency and confidentiality which is inherent with technical topics, and the difficulty for an official expertise institute to hold a dialogue with “outsiders” during an ongoing reviewing process in which it is participating. The pilot program, given its mixed results, also provided valuable lessons for further improvement of stakeholders’ involvement.
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McKinnon, Mikal A., i Leroy Stewart. "Demonstration and Licensing of a Spent Nuclear Fuel Dry Transfer System". W ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1175.
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Abstract Research studies by the Electric Power Research Institute (EPRI) established the technical and operational requirements necessary to enable the onsite cask-to-cask dry transfer of spent nuclear fuel. Use of the dry transfer system has the potential to permit shutdown reactor sites to decommission pools and provide the capability of transferring assemblies from storage casks or small transportation casks to sealed transportable canisters. Following an evaluation by the Department of Energy (DOE) and the National Academy of Sciences, a cooperative program was established between DOE and EPRI, which led to the cost-shared design of a dry transfer system (DTS). EPRI used Transnuclear, Inc., of Hawthorne, New York, to design the DTS in accordance with the technical and quality assurance requirements of the code of Federal Regulations, Title 10, Part 72 (10CFR72). EPRI delivered the final design report to DOE in 1995 and the DTS topical safety analysis report (TSAR) in 1996. DOE submitted the TSAR to the United States Nuclear Regulatory Commission (NRC) for review under 10CFR72 and requested that the NRC staff evaluate the TSAR and issue a Safety Evaluation Report (SER) that could be used and referenced by an applicant seeking a site-specific license for the construction and operation of a DTS. DOE also initiated a cold demonstration of major subsystem prototypes in 1996. After careful assessment, the NRC agreed that the DTS concept has merit. However, because the TSAR was not site-specific and was lacking some detailed information required for a complete review, the NRC decided to issue an Assessment Report (AR) rather than a SER. This was issued in November 2000. Additional information that must be included in a future site-specific Safety Analysis Report for the DTS is identified in the AR. The DTS consists of three major sections: a Preparation Area, a Lower Access Area, and a Transfer Confinement Area. The Preparation Area is a sheet metal building where casks are prepared for loading, unloading, or shipment. The Preparation Area adjoins the Lower Access Area and is separated from the Lower Access Area by a large shielded door. The Lower Access Area and Transfer Confinement Area are contained within concrete walls approximately three feet thick. These are the areas where the casks are located and where the fuel is moved during transfer operations. A floor containing two portals separates the Lower Access Area and the Transfer Confinement Area. The casks are located below the floor, and the fuel transfer operation occurs above the floor. The cold demonstration of the DTS was successfully conducted at the Idaho National Engineering and Environmental Laboratory (INEEL) as a cooperative effort between the DOE and EPRI. The cold demonstration was limited to the fuel handling equipment, the cask lid handling equipment, and the cask interface system. The demonstration included recovery operations associated with loss of power or off-normal events. The demonstration did not include cask receiving and lid handling; cask transport and lifting; vacuum/inerting/leak test; canister welding; decontamination; heating, ventilation, and air conditioning; and radiation monitoring. The demonstration test was designed to deliberately challenge the system and determine whether any specific system operation could adversely impact or jeopardize the operation or safety of any other function or system. All known interlocks were challenged. As in all new systems, there were lessons learned during the operation of the system and a few minor modifications made to ease operations. System modifications were subsequently demonstrated. The demonstration showed that the system operated as expected and provided times for normal fuel transfer operations. The demonstration also showed that recovery could be made from off-normal events.
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Dean, Jason, i David Rossiter. "Delivering Step Change Improvements to UK Low Level Waste Strategy". W ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16188.
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The UK Nuclear Industry continues to produce significant quantities of Low Level Waste (LLW) as decommissioning projects generating waste become more prevalent. Current infrastructure and projected increasing waste volumes will deliver a volumetric shortfall of storage capacity in the near future. Recently established as a stand alone site licence company, the Low Level Waste Repository (LLWR) near Drigg, in West Cumbria (formerly operated and owned by British Nuclear Group) is tasked with managing the safe treatment and disposal of LLW in the UK, on behalf of the Nuclear Decommissioning Authority (NDA). The problem is complex involving many stakeholders with potentially different priorities. Previously, most nuclear waste generators operated independently with limited integration with other similar organisations. However, the current financial, programme and technical pressures require collaborative working to facilitate a step-change improvement in LLW management. Achieving this quickly is as much of a challenge as delivering robust cost effective technical solutions. NDA is working in partnership with LLWR to develop a LLW Strategy for the Nuclear Industry and has in parallel commissioned a number of studies by the National Nuclear Laboratory (NNL), looking at opportunities to share best practice. A National Strategy Group has been established to develop a working partnership between the Nuclear Decommissioning Authority, LLW Repository Ltd, Regulators, Stakeholders and LLW Consignors, promoting innovation, value for money, and robust implementation of the waste hierarchy (avoid-reduce-re-use-recycle). Additionally the LLWR supported by the NNL have undertaken a comprehensive strategic review of the UK’s LLW management activities. Initial collaborative work has provided for the first time a detailed picture of the existing strategic baseline and identified significant national benefits from improving the way LLW is forecasted, characterised, segregated, and treated in line with the waste hierarchy. Implementation of volume reduction technologies, such as incineration and metal treatment, is critical to mitigate the LLWR capacity gap and reduce NDA’s liabilities. The cumulative effect of these solutions has the potential to reduce lifetime costs by several £billion and extend the life of the existing LLWR site to 2070 and possibly beyond. This work has informed the NDA’s UK Nuclear Industry LLW Strategy, published for consultation in June 2009 and the Draft UK LLW Management Plan which sets out how the strategy will be implemented. Technical and infrastructure solutions have been found to exist via the supply chain supporting deliver of the necessary step changes in the near future. Work continues to reduce the LLW inventory forecast uncertainties and evaluate strategic implementation options in more detail, e.g. benefits of national vs. local treatment and disposal solutions, plus on gaining the corresponding stakeholder acceptance and operational authorisations.
Raporty organizacyjne na temat "Nuclear Waste Technical Review Board"
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Rathbun, R. SRTC criticality technical review: Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility`s Waste Handling Facility. Office of Scientific and Technical Information (OSTI), październik 1993. http://dx.doi.org/10.2172/10196085.
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