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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.