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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Fighting fatigue and maintaining 10 CFR Part 26 compliance
Fatigue has been identified as a major risk factor in industrial accidents. According to the National Safety Council, 13 percent of workplace injuries can be attributed to fatigue.1 Other research indicates that working 12 hours per day is associated with a staggering 37 percent increase in risk of injury.2 Considering fatigue was a contributing factor to major nuclear accidents at Chernobyl and Three Mile Island, it makes sense that the Nuclear Regulatory Commission imposes hefty fines to ensure strict adherence to its fatigue management regulations—particularly, Code of Federal Regulations Title 10, Part 26, “Fitness for Duty Programs.”
Jean Baccou, Jinzhao Zhang, Philippe Fillion, Guillaume Damblin, Alessandro Petruzzi, Rafael Mendizábal, Francesc Reventos, Tomasz Skorek, Mathieu Couplet, Bertrand Iooss, Deog-Yeon Oh, Takeshi Takeda, Nils Sandberg
Nuclear Science and Engineering | Volume 194 | Number 8 | August-September 2020 | Pages 721-736
Technical Paper | doi.org/10.1080/00295639.2020.1759310
Articles are hosted by Taylor and Francis Online.
Uncertainty analysis is a key element in nuclear power plant deterministic safety analysis using best-estimate thermal-hydraulic codes and best-estimate-plus-uncertainty methodologies. If forward uncertainty propagation methods have now become mature for industrial applications, the input uncertainty quantification (IUQ) on the physical models still requires further investigations. The Organisation for Economic Co-operation and Development/Nuclear Energy Agency PREMIUM project attempted to benchmark the available IUQ methods, but observed a strong user effect due to the lack of best practices guidance. The SAPIUM project has been proposed toward the construction of a clear and shared systematic approach for IUQ. The main outcome of the project is a first “good-practices” document that can be exploited for safety study in order to reach consensus among experts on recommended practices as well as to identify remaining open issues for further developments. This paper describes the systematic approach that consists of five elements in a step-by-step approach to perform a meaningful model IUQ and validation as well as some good-practice guideline recommendations for each step.