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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Joonas Linnosmaa, Janne Valkonen (VTT Technical Research Center of Finland), Peter Karpati, André Hauge, Fabien Sechi, Bjørn Axel Gran (OECD)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 276-289
Complexity of modern control and safety systems challenge the usual linear document-based presentation of system design. This complicates the work of designers, assessors and regulators comprehending the system, whose understanding often depends on building a mental model of the system and thus assessing its suitability. More rigorous and structured way to represent the system, than the linear documents-based, is model-based approach. Based on a literature review, SysML and AADL were identified as suitable candidates. They were tried in an exploratory case study modelling APR1400 reactor protection system, based on its linear description from a real applicant’s design control document. Effort was also taken to extract safety assurance information (for independence) from the documentation and organize it into a structured safety argument. Research serves also to discuss the strengths and weaknesses of model-based specification and assessment compared to document-based approaches. Modelling of the system based on design document and extracting safety assurance information was challenging. Results, based on the modelling experiences and literature review, argue that the studied architecture languages offer benefits over the use of natural language in clarity, ambiguity and traceability. However, using these architecture description languages require extensive modelling expertise and effort to allow a smooth modelling process and understanding. In addition, multidisciplinary insight into the system at both the conceptual level as well as hardware and software level is required. We also identified support of classical safety analysis methods within SysML and AADL.