nuclear power safety Articles
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The Russian approach to nuclear liability
This paper gives a view of the challenges of nuclear liability in the specific context of the Russian Federation's legal system. Starting from the Chernobyl disaster and the benefits of nuclear energy, a detailed examination of the development of both internal law and international law regulating nuclear liability matters in Russia is given. Special attention is paid to the regimes established by ...
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An examination of nuclear power plants event reporting in the context of knowledge management
Challenges to the safety of operating nuclear power plants due to ageing, power uprates, modernisations and a generational exchange in the workforce put a strong focus on knowledge. Both the nuclear regulators and the nuclear plant operators need to learn more about knowledge management in order to better manage knowledge. This paper aims to promote implementation of knowledge management by ...
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Improvement in modelling ZED–2 critical experiments using WIMS–AECL/RFSP
The ZED–2 experiments were used for the validation of the WIMS–AECL/RFSP code suite. Two RFSP models (using the cross–sections provided by the WIMS–AECL lattice code) were constructed; one model used for calculations of regions just up to the critical heights, while the other model simulated explicitly the unmoderated region (called Improved Model herein). Results of the comparison between these ...
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Analysis study for nanotechnology promotions in the nuclear industry using system dynamics
The investment in the nuclear industry by nanoscale technology is investigated. For marketing innovations, the consideration of the risks and benefits in the industry is important. For the promotion of a new technology, it is necessary to improve the safety standard of this technology, and the Risk Assessment (RA) of nanotechnology (NT) is an important step in the application of nanoscale ...
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Nuclear knowledge management and preservation in Lithuania
Problems of nuclear knowledge management and preservation in Lithuania are presented in the paper. The support provided through bilateral cooperation projects was very important for Lithuania. The main projects implemented in the last 14 years are described in this paper. Lithuania joined INIS (International Nuclear Information System) in 1994 and established its own INIS national centre in the ...
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The framework structure and fuzzy processing of a nuclear emergency decision-making evaluation system (ESY)
This paper discusses the construction of ESY, a combination of 'Real-time Online Decision-making Support System' (RODOS) which was developed by the European Community as the basis of such software as decision-making analysis, fuzzy mathematics, etc. This paper also discusses the information structure of ESY expressed in the united data model and the application of fuzzy decision-making theory and ...
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Public perception and attitude of the young generation towards nuclear energy and its safety in South Korea
Safety of nuclear power plants became a primary concern after the Fukushima accident. Public perception and attitude towards nuclear power has been considered an important factor that can influence the future development of nuclear energy. However, there are few empirical researches studying those issues. To explore those issues, this paper uses data collected from sets of interviews with ...
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NUTEMA: a tool for supervising nuclear technology and for the transfer of knowledge
In this paper is presented NUTEMA (Nuclear Power Plant Technology Management System) an IT innovative system dealing with the nuclear technology. The overall goal is to offer a framework capable to present in one room whatever is concerned with a Nuclear Power Plant (NPP) unit implementing together a multilevel and multi–view user access according to enterprise architecture models. The NUTEMA ...
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Regulations and standards for the measurement of performance and management of ageing of I&C systems of nuclear power plants
Instrumentation and Control (I&C) equipment is vital to the safety and viability of nuclear power plants. This equipment must provide accurate and timely measurements of plant control and safety systems to ensure efficient operation and guard against mishaps. Given this, numerous regulations, standards and guidelines have been devised to formulate requirements and establish maintenance methods to ...
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Reflections on regulatory oversight of nuclear power plants
A regulatory body acts as a representative for society to ensure that the operation of nuclear facilities do not introduce any undue threats. Typical regulatory tasks include the definition of safety requirements, the inspections needed to ensure that they are adhered to and the imposing of sanctions if violations are detected. Regulatory oversight is anchored in national legislation, which is ...
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On system validity, quasi-experiments, and safety: a critique of NUREG/CR-6393
Based on the methods of Cook and Campbell (1979), a quasi-experimental validation model for complex human–machine systems has been recommended for the final evaluation of nuclear power plant control rooms (O'Hara et al., 1997). This model-based approach to validating systems and assuring safety is critiqued in terms of experimental theory and engineering practice. It is concluded that the model ...
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Proprietary electronics for reactor safety and controls
India was one of the first countries in the world to have realised a computer-based reactor protection system. It was in the late 1980s when fully fledged microprocessor-based reactor protection units were commissioned for research and then for power reactors. Since then the proprietary philosophy, applied to have proprietary electronics in reactor protection and control, has expanded to include ...
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Need for restoration of the nuclear knowledge management in Serbia
Nuclear programmes in former Yugoslavia have been supported by comprehensive research and development (R&D), educational programmes and pertinent training in the country and abroad. Three research reactors and one nuclear power plant (NPP) were constructed and operated with the significant participation of domestic experts. Since 1989, the nuclear expertise has deteriorated considerably in ...
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Safety assessment for the deficient operation data in the gas-cooled nuclear power plants for hydrogen production
The probabilistic safety assessment (PSA) is investigated in the case of the operational data shortage which is characteristic of the passive system in gas-cooled nuclear power plants (NPPs). Therefore, it is difficult to make a quantification of the PSA. One of the solutions is to compare the passive system and the active system. Using this comparison, one can find the priority of the passive ...
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Evaluation of the programme for long–term operation for safety requirements during operational safety
The programme for long–term operation (LTO) in the nuclear power plant (NPP) installations is one of the essential nuclear safety concerns. It may be defined as an operation beyond an established time frame set forth by, for example, licence term, design, standards, licence and/or regulations, which has been justified by safety assessment, with consideration given to life–limiting processes and ...
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Historical, regulatory and safety aspects of nuclear energy in India
Jawaharlal Nehru, former Prime Minister of India and Homi J. Bhabha interacted closely to set up the Atomic Energy Commission in 1948. The Indian parliament replaced the Atomic Energy Act, 1948 with the Atomic Energy Act, 1962 (AEA 1962) and promulgated appropriate rules. The Department of Atomic Energy (DAE) was set up in 1954. The Indian Cabinet established, through a resolution, a new Atomic ...
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Experience with the operation, maintenance and utilisation of the 3 MW TRIGA Mark-II research reactor of Bangladesh
The 3 MW TRIGA (Training, Research, Isotope, General Atomics) Mark-II research reactor of the Bangladesh Atomic Energy Commission (BAEC) has been operating at Atomic Energy Research Establishment (AERE), Savar, Dhaka, since September 1986. Since its commissioning, the reactor has been used in various fields of research and utilisation, such as Neutron Activation Analysis (NAA), Neutron ...
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Failure possibilities for nuclear safety assessment by fault tree analysis
Fault tree analysis (FTA) is a deductive tool to assess the safety of nuclear power plants. This analysis can only be implemented if all basic events in the tree have their corresponding failure rates. Therefore, safety analysts have to provide those failure rates well in advance. However, it is often difficult to obtain those failure rates due to insufficient data, changing environment or new ...
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Reprocessing of AHWR spent-fuel: challenges and strategies
Reprocessing of advanced heavy water reactor (AHWR) spent-fuel involves separation of Th, 233U and Pu, from the fission products and from one another. A proper combination of Purex and Thorex processes is required. The technology development for a reprocessing facility is extremely complex owing to high fissile content, high levels of irradiation, presence high of levels of 232U, difficulty in ...
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An empirical study of nuclear power–related knowledge flow after Fukushima
Fukushima nuclear power plant accident has become a hot topic in debates among professional communities. It also caused knowledge searching and knowledge sharing among social groups. However, there is a lack of empirical studies investigating nuclear power–related knowledge flow in social communities. This paper examines nuclear power–related knowledge flow by focusing on the case of college ...
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