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OECD/NEA ARC-F Project: Summary of Fission Product Transport

  • Terttaliisa Lind*
  • , Jarmo Kalilainen
  • , Catherine Marchetto
  • , Sara Beck
  • , Koichi Nakamura
  • , Chiaki Kino
  • , Yu Maruyama
  • , Kentaro Kido
  • , Sung Il Kim
  • , Yoonhee Lee
  • , Luis E. Herranz
  • , Kirill Dolganov
  • *Corresponding author for this work
  • Paul Scherrer Institute
  • Autorité de sûreté nucléaire et de radioprotection
  • GRS
  • Central Research Institute of Electric Power Industry
  • The Institute of Applied Energy
  • JAEA
  • Korea Atomic Energy Research Institute
  • KINS
  • CIEMAT
  • IBRAE

Research output: Contribution to conferenceConference paperpeer-review

Abstract

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.

Original languageEnglish
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages4796-4809
Number of pages14
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: 2023.08.202023.08.25

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period23.08.2023.08.25

Keywords

  • ARC-F
  • Fission Products
  • Fukushima

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