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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Takuya Yamashita, Ikken Sato, Takeshi Honda, Kenichiro Nozaki, Hiroyuki Suzuki, Marco Pellegrini, Takeshi Sakai, Shinya Mizokami
Nuclear Technology | Volume 206 | Number 10 | October 2020 | Pages 1517-1537
Technical Paper | doi.org/10.1080/00295450.2019.1704581
Articles are hosted by Taylor and Francis Online.
Estimation and understanding of the state of the fuel debris and fission products inside the plant comprise an essential step in the decommissioning of Tokyo Electric Power Company Holdings’ Fukushima Daiichi nuclear power station (1F). However, because of the plant’s high-radiation environment, direct observation of the plant interior is difficult. Therefore, in order to understand the plant’s interior conditions, comprehensive analysis and evaluation 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 are necessary. These evaluations can be used to estimate the conditions of the interior of the reactor pressure vessel (RPV) and the primary containment vessel (PCV). This paper addresses 1F Unit 2 as the subject to produce an estimated map of the fuel debris distribution from data obtained about the RPV and PCV based on comprehensive evaluation of various measurement data and information obtained from the accident progression analysis, which were released to the public in June 2018.