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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Latest News
DOE opens funding opportunity for HALEU transport packages
The Department of Energy announced November 19 that up to $16 million is available through a new High-Assay Low-Enrichment Transportation Package funding opportunity to research, develop, and acquire Nuclear Regulatory Commission licensing for transportation of HALEU—using new or modified packages.
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.