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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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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.
Kenji Mashio, Mizuki Kasamatsu, Eisuke Noda
Nuclear Technology | Volume 209 | Number 3 | March 2023 | Pages 346-353
Technical Paper—Human-Machine Interface Technologies | doi.org/10.1080/00295450.2022.2087837
Articles are hosted by Taylor and Francis Online.
Mitsubishi Heavy Industries, Ltd. has developed a computer-aided decision-making supporting panel system called DMP to support decision making of management staff in nuclear power plants by presenting associated information (e.g., plant situation and on-site/off-site conditions) in an organized and timely manner during emergency conditions. DMP will be located on-site as well as at an office off-site and will present associated information for staff and managers to share information and promote communications. DMP has been developed considering lessons learned from the Fukushima Daiichi accident including situation awareness distraction and workload issues under severe accidents. It was recognized that it is difficult to collect, organize, and analyze plant data and associated information under high-stress conditions and a severely degraded work environment. DMP will collect plant status information using plant chronological data logs and associated information, such as site situations (e.g., various kinds of information showing damaged equipment and hazard area, etc.), verbal/written status reports, and communication logs among staffs who perform corresponding actions at the site. DMP has been developed using a human-centered design approach based on International and Japanese human factors engineering design guidance (i.e., IEC 60964, “Nuclear Power Plants – Control Rooms – Design,” and JEAG 4617, “Guideline for Development and Design of Computerized Human-Machine Interface in the Central Control Room”) and verified with human factors verification (task support verification) to ensure the DMP support decision-making process. DMP will be workable to organize and present the current situations and recommendations to staff with collected data and policies/rules in emergency management plans.