Nuclear facility regulation
173 resources related to Nuclear facility regulation
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The Pulsed Power Conference is held on a biannual basis and serves as the principal forum forthe exchange of information on pulsed power technology and engineering.
2020 IEEE 17th International Symposium on Biomedical Imaging (ISBI 2020)
The IEEE International Symposium on Biomedical Imaging (ISBI) is the premier forum for the presentation of technological advances in theoretical and applied biomedical imaging. ISBI 2020 will be the 17th meeting in this series. The previous meetings have played a leading role in facilitating interaction between researchers in medical and biological imaging. The 2020 meeting will continue this tradition of fostering cross-fertilization among different imaging communities and contributing to an integrative approach to biomedical imaging across all scales of observation.
2020 IEEE 18th International Conference on Industrial Informatics (INDIN)
INDIN focuses on recent developments, deployments, technology trends, and research results in Industrial Informatics-related fields from both industry and academia
IEEE International Conference on Plasma Science (ICOPS) is an annual conference coordinated by the Plasma Science and Application Committee (PSAC) of the IEEE Nuclear & Plasma Sciences Society.
The 2020 IEEE International Conference on Systems, Man, and Cybernetics (SMC 2020) will be held in Metro Toronto Convention Centre (MTCC), Toronto, Ontario, Canada. SMC 2020 is the flagship conference of the IEEE Systems, Man, and Cybernetics Society. It provides an international forum for researchers and practitioners to report most recent innovations and developments, summarize state-of-the-art, and exchange ideas and advances in all aspects of systems science and engineering, human machine systems, and cybernetics. Advances in these fields have increasing importance in the creation of intelligent environments involving technologies interacting with humans to provide an enriching experience and thereby improve quality of life. Papers related to the conference theme are solicited, including theories, methodologies, and emerging applications. Contributions to theory and practice, including but not limited to the following technical areas, are invited.
Contains articles on the applications and other relevant technology. Electronic applications include analog and digital circuits employing thin films and active devices such as Josephson junctions. Power applications include magnet design as well asmotors, generators, and power transmission
Specific topics of interest include, but are not limited to, sequence analysis, comparison and alignment methods; motif, gene and signal recognition; molecular evolution; phylogenetics and phylogenomics; determination or prediction of the structure of RNA and Protein in two and three dimensions; DNA twisting and folding; gene expression and gene regulatory networks; deduction of metabolic pathways; micro-array design and analysis; proteomics; ...
Physics, medicine, astronomy—these and other hard sciences share a common need for efficient algorithms, system software, and computer architecture to address large computational problems. And yet, useful advances in computational techniques that could benefit many researchers are rarely shared. To meet that need, Computing in Science & Engineering (CiSE) presents scientific and computational contributions in a clear and accessible format. ...
Research, development, design, application, construction, installation, and operation of electric power generating facilities (along with their conventional, nuclear, or renewable sources) for the safe, reliable, and economic generation of electrical energy for general industrial, commercial, public, and domestic consumption, and electromechanical energy conversion for the use of electrical energy
Management of technical functions such as research, development, and engineering in industry, government, university, and other settings. Emphasis is on studies carried on within an organization to help in decision making or policy formation for RD&E.
Conference Record for 1992 Fifth Conference on Human Factors and Power Plants, 1992
The authors report on a program to evalute the human factors portions of the GE Advanced Boiling Water Reactor (ABWR), CE System 80+, and Westinghouse AP-600 advanced reactor designs. These reviews are being conducted to ensure that the man-machine interfaces for advanced reactor control facilities are consistent with accepted human factors principles and practices, and that the design features will ...
IEEE Power Engineering Review, 1982
Proceedings of the 1997 IEEE Sixth Conference on Human Factors and Power Plants, 1997. 'Global Perspectives of Human Factors in Power Generation', 1997
Insights and improvements realized through implementing the Maintenance Rule at Millstone nuclear power station (USA) are presented. The Maintenance Rule is being used to support unit restart through demonstrated improvement in regulatory compliance activities and improved system performance. The system performance aspect of this paper focuses on the Maintenance Rule Goal Setting process with an emphasis on performance issues related ...
Proceedings of the 22nd Annual International Conference of the IEEE Engineering in Medicine and Biology Society (Cat. No.00CH37143), 2000
The U.S. Nuclear Regulatory Commission (NRC) issues licenses to users of byproduct materials in 21 states and the District of Columbia. The regulations governing the possession and use of these products are found in Title 10 of the Code of Federal Regulations (10 CFR) specifically Parts 19, 20, 30 and 35 for medical use of radionuclides. Some areas are clear ...
Conference Record of the 1991 IEEE Nuclear Science Symposium and Medical Imaging Conference, 1991
Advanced nuclear power plants must achieve higher levels of safety than the first generation of plants. Showing that this is indeed true provides new challenges to reliability and risk assessment methods in the analysis of the designs employing passive and semipassive protection. Reliability assurance of the advanced reactor system is important for determining the safety of the design and for ...
The Benefits of Using IEEE Nuclear Standards: A Multi-Stakeholder View (webinar)
A Nuclear Waste Repository Grows In Finland
Larson Collection interview with William Alfred Fowler
Landing in a Self-Flying Airplane. Ready for it? - Antonio Crespo
Robotics History: Narratives and Networks Oral Histories:Ron Daniel
The Full Spectrum: Travelogue of the Atomic Age
Robotics History: Narratives and Networks Oral Histories: Red Whittaker
NREL Wind Technology Center
Larson Collection interview with Edward Teller
Atom Smasher Dedication
Interaction of ferromagnetic and superconducting permanent magnets - superconducting levitation
Overview of Lawrence Livermore National Laboratory Campus Power System
The Full Spectrum: Wireless Power Roundup
Mayo Clinic Motion Lab
Renewable Power for Refugee Camps
Opening Chat: Rod Beckstrom and Xiaodong Lee - ETAP Beijing 2016
Life on 150 Watts with a nano-hydroelectric turbine
Larson Collection interview with Alvin Weinberg
Brooklyn 5G - 2015 - Mr. Mikael Hook - Bringing Massive MIMO to Reality
The authors report on a program to evalute the human factors portions of the GE Advanced Boiling Water Reactor (ABWR), CE System 80+, and Westinghouse AP-600 advanced reactor designs. These reviews are being conducted to ensure that the man-machine interfaces for advanced reactor control facilities are consistent with accepted human factors principles and practices, and that the design features will meet regulatory requirements for design certification. These reviews are conducted using existing guidance and review criteria under development for application to emerging technologies such as the use of electroluminescent displays and on-screen controls. As part of the review and the vendor's design, inspections, tests, and analyses are being developed to ensure that the resulting control facilities are built to adequately support operator performance under all plant conditions.<<ETX>>
Insights and improvements realized through implementing the Maintenance Rule at Millstone nuclear power station (USA) are presented. The Maintenance Rule is being used to support unit restart through demonstrated improvement in regulatory compliance activities and improved system performance. The system performance aspect of this paper focuses on the Maintenance Rule Goal Setting process with an emphasis on performance issues related to human factors. The causes and corrective actions for unacceptable performance on select Millstone station systems are discussed.
The U.S. Nuclear Regulatory Commission (NRC) issues licenses to users of byproduct materials in 21 states and the District of Columbia. The regulations governing the possession and use of these products are found in Title 10 of the Code of Federal Regulations (10 CFR) specifically Parts 19, 20, 30 and 35 for medical use of radionuclides. Some areas are clear and not likely to be misinterpreted but, there are some sections which may be interpreted in several ways. At our institution one of the reasons a Severity Level III violation was issued was due to the radiation safety officer's (RSO) interpretation of the regulation. A package containing 2 millicuries of iodine-125 was lost due to personnel not following established policies for the receipt of radioactive material. The RSO failed to notify NRC immediately because he did not think the criteria for immediate notification as stated in 10 CFR Part 20.2201 had been met. Part 20.2201 states that a licensee shall report by telephone immediately after its occurrence becomes known to the licensee any lost, stolen or missing licensed materials greater than specified quantities if it appears that an exposure could result to persons in unrestricted areas. It is important to keep abreast of the philosophy of the NRC and the areas that are of current interest to avoid violations. With the increase in the incidents of deliberate misuse of isotopes at medical or research facilities, NRC is wary of radioisotopes being tampered with and misused.
Advanced nuclear power plants must achieve higher levels of safety than the first generation of plants. Showing that this is indeed true provides new challenges to reliability and risk assessment methods in the analysis of the designs employing passive and semipassive protection. Reliability assurance of the advanced reactor system is important for determining the safety of the design and for determining the plant operability. Safety is the primary concern, but operability is considered indicative of good and safe operation. The authors discuss several concerns for reliability assurance of the advanced design, encompassing reliability determination, level of detail required in advanced reactor submittals, data for reliability assurance, systems interactions and common cause effects, passive component reliability, PRA- based configuration control system, and inspection, training, maintenance, and test requirements. Suggested approaches are provided for addressing each of these topics.<<ETX>>
Protein glycosylation is one of the most common posttranslational modifications (PTMs) with several types. O-GlcNAcylation is an O-linked glycosylation with attachment of beta-N-acetylglucosamine (GlcNAc) to Ser/Thr residues catalyzed by O-GlcNAc transferase (OGA), whose removal is catalyzed by O-GlcNAcase. Unlike mucin-type O-glycosylation, O-GlcNAcylation occurs primarily in nucleocytoplasmic proteins and the monosaccharide is not further extended. Moreover, O-GlcNAcylation is dynamic and often reciprocal to phosphorylation at the same or adjacent Ser/Thr residues. Growing evidences suggest that O-GlcNAcylation is very common and has broad roles in physiology as well as in diseases especially through its interplay with phosphorylation, e.g., regulation of insulin signaling, transcription, and roles in diabetes and neurodegenerative diseases. In contrast to the enormous body of research on cellular roles of phosphorylation, the amount of research on O-GlcNAcylation has been disproportionally small and annotation of O-GlcNAcylated sites in protein databases is currently scarce. An O-GlcNAcylation site prediction program was developed in 2002, but it was based on a small data set with 40 O-GlcNAcylation sites known at that time. Here we seek to develop a database of O-GlcNAcylated proteins and sites, named dbOGAP, and also an O-GlcNAcylated site prediction system based on known sites data in dbOGAP to facilitate annotation and proteomic identification of the O-GlcNAcylation sites. We developed dbOGAP based primarily on O-GlcNAcylated proteins and sites published in peer-reviewed articles dated back to 1984 since it was first described. Most of these proteins were mapped to the UniProtKB protein IDs, except for some that could not be unambiguously mapped. The database currently contains 540 protein entries with experimental O-GlcNAcylation information, and 338 O-GlcNAc sites for 164 proteins. About 59% of these proteins are of humans, and other organisms include rat, mouse, fly and African frog. Among 164 proteins with known O-GlcNAcylation sites, 122 also have both phosphorylation (total 1634) and O-GlcNAc sites (total 263). The gene ontology (GO) profiling showed that the known O-GlcNAcylated proteins have a broad range of functions including developmental process, transcriptional regulation, cell signaling, metabolic regulation, and cellular transport and trafficking. The GO profile also showed that O-GlcNAcylated proteins are primarily nuclear and cytoplasmic, including membrane-associated intracellular proteins. The database is also populated with additional orthologous protein sequences to known O-GlcNAcylated proteins. Additional functional data, including other PTM features, biological pathways and disease information have been integrated to the database. We developed an O-GlcNAcylation site prediction program using support vector machine (SVM). As positive instances, sequence fragments surrounding 322 O-GlcNAcylated Ser/Thr sites were extracted from 157 proteins in dbOGAP, and over 28 thousand sequence fragments surrounding the rest of the Ser/Thr sites in those proteins were assumed as negative instances. Two thirds of this data set was randomly selected as development data and was used for tuning parameters in SVM classifiers, while the rest of the data was set apart as a held-out test data set. To reduce the impact of imbalanced data on the performance of trained classifiers, we explored different ratio of positive to negative instances in a training data set, which was controlled by under-sampling negative instances in a training data set. The optimal parameters of the prediction system were sought in five-fold cross-validation tests conducted on the development data set, and the final classifier trained on the entire development data set was evaluated on the held-out test data set. We used four encoding methods for feature vector extraction, including binary encoding, composition of k-spaced amino acid pairs (CKSAAP), monomer spectrum (MS), and composition of monomer spectrum (CMS). These encoding methods yielded different prediction performance for O-GlcNAcylation sites. The results showed that the method obtained an AUC (area under curve) of ~80% on the test sequence set. The dbOGAP database and the O-GlcNAcylation site prediction program tool are being made Web accessible and the Web resource will be an important bioinformatics tool to facilitate exploration of the broad roles of O-GlcNAcylation in physiology and diseases.
The status of the Nuclear Regulatory Commission's (NRC's) maintenance rule and regulatory guide, the usefulness of risk considerations to help focus maintenance, and the importance of human activities in maintenance are discussed. The opinions and viewpoints expressed are the authors' personal ones, and do not necessarily reflect the policy of the US Nuclear Regulatory Commission.<<ETX>>
This paper presents the regulatory review process for seismic and dynamic qualification of safety-related electrical and mechanical equipment in nuclear power plant design, and highlights those areas that need careful attention in a qualification program. Qualification requirements as embodied in the General Design Criterion 2, Appendix A to the Code of Federal Regulations (CFR) 10 Part 50, VI(a) (1) and (2) of Appendix A to 10 CFR Part 100, and the Standard Review Plan Section 3.10 are reviewed. In addition, the review procedure of seismic qualification review team (SQRT) is described. In the past years of SORT review of near term operating license (NTOL) plants, some problem areas have been identified regarding applicant's equipment seismic and dynamic qualification programs. In this paper, the problem areas which are of generic nature are discussed. Among the areas covered are: shake-table input wave forms, consideration of hydrodynamic loads, sequential testing procedure, surveillance and maintenance program, fatigue cycling effects, qualification of mechanical equipment, site-specific earthquakes, auditability of qualification documents, update of final safety analysis report and documentation filing system.
The authors describe a recently completed project for the Electric Power Research Institute (EPRI) and the utility industry, the aim of which was to develop a method for evaluating the potential operational impact of discrepancies between nuclear power plant training simulators and their reference plants. The goal of the method is to decrease the probability of errors in the actual control room that can be attributed to differences, encountered during training, between the simulator and the plant. Considerations in the method include: the criticality of operator tasks associated with the discrepancy; the obviousness of the discrepancy to the least experienced, qualified operator; and the potential for plant recovery from an operational error. After these considerations are evaluated, assignment of an impact rating can be made. Practical considerations such as training schedule and potential for training around the discrepancy were also considered.<<ETX>>
This standard provides the basic principles for design qualification of safety systems equipment used in nuclear power generating stations.
This standard sets forth the minimum acceptable requirements for the performance of reliability analyses for safety-related systems when used to address the reliability considerations discussed in the standards listed in Clause 2. The methods of this standard may also be applied to other systems, including the interactions, if any, between safety-related and non-safety-related systems. The requirements should be applied during ...