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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
National Museum of Nuclear Science and History explores “atomic” culture
For many of us, the toys of our childhood leave indelible marks on our consciousness, affecting our long-term perceptions and attitudes about certain things. Hot Wheels may inspire a lifelong fascination with fast, flashy automobiles, while Barbies might shape ideas about beauty and self-image. For the generation who grew up during the Atomic Age—the post–World War II era from roughly the mid-1940s to the early 1960s—the toys, games, and entertainment of their childhoods might have included things like atomic pistols, atomic trains, rings with tiny amounts of radioactive elements, and comic books, puzzles, and music about nuclear weapons.
Belal Almomani, Ahmad Ababneh, Muhammad Zubair
Nuclear Technology | Volume 209 | Number 2 | February 2023 | Pages 214-227
Technical Paper | doi.org/10.1080/00295450.2022.2133507
Articles are hosted by Taylor and Francis Online.
After the Three Mile Island Unit 2 accident, regulatory bodies were concerned about the safety measures in design and operation corresponding to the operator’s decisions and procedures for handling such off-normal transients. Several recommendations were proposed to analyze transients and accidents, improve and revise emergency operating procedures (EOPs), and conduct functional training. In this work, procedural paths were systematically studied to identify the problems in the diagnosis associated with a pilot-operated relief valve (PORV)–break loss-of-coolant accident (LOCA) as well as to suggest new indications for improving the EOPs. Operational parameters during PORV-break LOCA and pipeline-break small-break LOCA were analyzed using a generic pressurized water reactor simulator to compare and justify the symptoms between these two events. It was found that suggesting further indications mainly in the reactor cooling system and containment symptoms may improve the diagnosis of a PORV-break LOCA from the pipeline-break small-break LOCA. This paper presents a practical approach to evaluating diagnostic procedures to better understand operator recovery actions corresponding to reactor system response in dealing with a PORV-break LOCA.