TY - GEN
T1 - OECD/NEA ARC-F Project
T2 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
AU - Lind, Terttaliisa
AU - Kalilainen, Jarmo
AU - Marchetto, Catherine
AU - Beck, Sara
AU - Nakamura, Koichi
AU - Kino, Chiaki
AU - Maruyama, Yu
AU - Kido, Kentaro
AU - Kim, Sung Il
AU - Lee, Yoonhee
AU - Herranz, Luis E.
AU - Dolganov, Kirill
N1 - Publisher Copyright:
© 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.
PY - 2023
Y1 - 2023
N2 - The OECD/NEA ARC-F project was established to investigate the accidents at Fukushima Daiichi nuclear power station with the aim of consolidating the observations for deeper understanding of the severe accident progression and the status of reactors and containment vessels. Additionally, the project formed an information sharing framework in reactor safety between Japan and international experts. In order to achieve these objectives, the project focused on three tasks: i) to refine analysis for accident scenarios and associated fission-product transport and dispersion, ii) to compile and manage data on the Fukushima Daiichi NPS accident, and iii) to discuss future long-term projects relevant to the Fukushima Daiichi NPS accident. The work was carried out by 22 partners from 12 countries. In the fission product group, ten organizations worked on five topics which were ranked with a high significance as open issues based on the BSAF project, and were thereby selected for further investigations. The five fission product related topics were: i) fission product speciation, ii) iodine chemistry, iii) pool scrubbing, iv) fission product transport and behavior in the buildings, and v) uncertainty analysis and variant calculations. In this paper, the work carried out to investigate these five fission product release and transport topics of special interest in the ARC-F project are described and summarized.
AB - The OECD/NEA ARC-F project was established to investigate the accidents at Fukushima Daiichi nuclear power station with the aim of consolidating the observations for deeper understanding of the severe accident progression and the status of reactors and containment vessels. Additionally, the project formed an information sharing framework in reactor safety between Japan and international experts. In order to achieve these objectives, the project focused on three tasks: i) to refine analysis for accident scenarios and associated fission-product transport and dispersion, ii) to compile and manage data on the Fukushima Daiichi NPS accident, and iii) to discuss future long-term projects relevant to the Fukushima Daiichi NPS accident. The work was carried out by 22 partners from 12 countries. In the fission product group, ten organizations worked on five topics which were ranked with a high significance as open issues based on the BSAF project, and were thereby selected for further investigations. The five fission product related topics were: i) fission product speciation, ii) iodine chemistry, iii) pool scrubbing, iv) fission product transport and behavior in the buildings, and v) uncertainty analysis and variant calculations. In this paper, the work carried out to investigate these five fission product release and transport topics of special interest in the ARC-F project are described and summarized.
KW - ARC-F
KW - Fission Products
KW - Fukushima
UR - https://www.scopus.com/pages/publications/85195076361
U2 - 10.13182/NURETH20-40120
DO - 10.13182/NURETH20-40120
M3 - Conference paper
AN - SCOPUS:85195076361
T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
SP - 4796
EP - 4809
BT - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PB - American Nuclear Society
Y2 - 20 August 2023 through 25 August 2023
ER -