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Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Fusion Science and Technology
Latest News
ANS Standards Committee publishes joint ASME/ANS standard for Level 1/large early release frequency PRA
ANSI/ASME/ANS RA-S-1.1-2024, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, has been published by the American Nuclear Society. The document, which is a joint standard developed with the American Society of Mechanical Engineers by the ANS/ASME Joint Committee on Nuclear Risk Management, received the approval of the American National Standards Institute on February 29, 2024, and was issued on March 15, 2024.
A. C. Uggenti, G. F. Nallo, A. Carpignano, N. Pedroni, R. Zanino
Fusion Science and Technology | Volume 78 | Number 3 | April 2022 | Pages 186-198
Technical Paper | doi.org/10.1080/15361055.2021.1984720
Articles are hosted by Taylor and Francis Online.
A preliminary but systematic safety analysis of a liquid metal divertor (LMD) for the EU DEMO performed by means of the Functional Failure Mode and Effect Analysis (FFMEA) is presented. This methodology is suitable for the analysis of the LMD, which is undergoing preconceptual design. In fact, the FFMEA compensates for the lack of detailed design information by postulating the loss of a system function, rather than a specific component failure.
The implementation of the FFMEA led to a better understanding of the safety and operational issues associated with the system and to the identification of a list of postulated initiating events (PIEs), i.e., the most challenging conditions for the plant. The PIEs, together with their possible consequences, represent an input for future quantitative safety analyses. Due to the early design stage of the LMD and the iterative nature of the methodology, this list will evolve alongside the design detail and with improvements in the understanding of phenomena driving reactor behavior.
The study highlighted some safety-relevant issues, e.g., those related to materials compatibility and system modularity, to be addressed in the perspective of a safety-driven design evolution.