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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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August 2025
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The newest era of workforce development at ANS
As most attendees of this year’s ANS Annual Conference left breakfast in the Grand Ballroom of the Chicago Downtown Marriott to sit in on presentations covering everything from career pathways in fusion to recently digitized archival nuclear films, 40 of them made their way to the hotel’s fifth floor to take part in the second offering of Nuclear 101, a newly designed certification course that seeks to give professionals who are in or adjacent to the industry an in-depth understanding of the essentials of nuclear energy and engineering from some of the field’s leading experts.
Takuya Yamashita, Takeshi Honda, Masato Mizokami, Kenichiro Nozaki, Hiroyuki Suzuki, Marco Pellegrini, Takeshi Sakai, Ikken Sato, Shinya Mizokami
Nuclear Technology | Volume 209 | Number 6 | June 2023 | Pages 902-927
Technical Paper | doi.org/10.1080/00295450.2022.2157663
Articles are hosted by Taylor and Francis Online.
The estimation and understanding of the state of fuel debris and fission products inside the plant is an essential step in the decommissioning of the Tokyo Electric Power Company Holdings Fukushima Daiichi Nuclear Power Station (1F). However, the direct observation of the plant interior, which is under a high radiation environment, is difficult and limited. Therefore, in order to understand the plant interior conditions, a comprehensive analysis and evaluation are necessary, based on various measurement data from the plant, analysis of plant data during the accident progression phase, and information obtained from computer simulations for this phase. These evaluations can be used to estimate the conditions of the interior of the reactor pressure vessel (RPV) and the primary containment vessel (PCV). Herein, 1F Unit 3 is addressed as the subject to produce an estimated diagram of the fuel debris distribution from data obtained about the RPV and PCV based on the comprehensive evaluation of various measurement data and information obtained from the accident progression analysis, which were released to the public in November 2022.