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Lind, T.*; Kalilainen, J.*; Marchetto, C.*; Beck, S.*; 中村 康一*; 木野 千晶*; 丸山 結; 城戸 健太朗; Kim, S. I.*; Lee, Y.*; et al.
Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (Internet), p.4796 - 4809, 2023/08
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 will be described and summarized.
Herranz, L. E.*; Pellegrini, M.*; Lind, T.*; Sonnenkalb, M.*; Godin-Jacqmin, L.*; L
pez, C.*; Dolganov, K.*; Cousin, F.*; 玉置 等史; Kim, T. W.*; et al.
Nuclear Engineering and Design, 369, p.110849_1 - 110849_7, 2020/12
被引用回数：20 パーセンタイル：94.29(Nuclear Science & Technology)OECD/NEAプロジェクト"福島第一原子力発電所事故に関するベンチマーク研究"のフェーズ2は2015年中期に開始された。このプロジェクトの目的は、解析期間を地震発生から3週間に拡張、核分裂生成物(FP)の挙動や環境への放出、そして放射線に関するデータや逆解析によるソースターム推定等の様々なデータとの比較を行うことである。6か国9組織が異なるシビアアクシデント解析コードを用いて1号機の事故解析を行った。本報告では、参加機関の1号機の解析結果やプラントデータとの比較から得られた知見、事故進展の評価及び最終的な原子炉内の状態について述べる。特に原子炉圧力容器の状態、溶融炉心の放出及びFP挙動及び放出について焦点を当てる。また、1号機特有の事柄に焦点を当て、不確かさや必要となるデータも含めコンセンサスを得た点についてまとめる。
Pellegrini, M.*; Herranz, L.*; Sonnenkalb, M.*; Lind, T.*; 丸山 結; Gauntt, R.*; Bixler, N.*; Morreale, A.*; Dolganov, K.*; Sevon, T.*; et al.
Nuclear Technology, 206(9), p.1449 - 1463, 2020/09
被引用回数：35 パーセンタイル：98.28(Nuclear Science & Technology)The OECD/NEA Benchmark Study at the Accident of Fukushima Daiichi Nuclear Power Station (BSAF) project, which started in 2012 and continued until 2018, was one of the earliest responses to the accident at Fukushima Daiichi. The project, divided into two phases addressed the investigation of the accident at Unit 1, 2 and 3 by Severe Accident (SA) codes until 500 h focusing on thermal-hydraulics, core relocation, Molten Corium Concrete Interaction (MCCI) and fission products release and transport. The objectives of BSAF were to make up plausible scenarios based primarily on SA forensic analysis, support the decommissioning and inform SA codes modeling. The analysis and comparison among the institutes have brought up vital insights regarding the accident progression identifying periods of core meltdown and relocation, Reactor Pressure Vessel (RPV) and Primary Containment Vessel (PCV) leakage/failure through the comparison of pressure, water level and CAMS signatures. The combination of code results and inspections (muon radiography, PCV inspection) has provided a picture of the current status of the debris distribution and plant status. All units present a large relocation of core materials and all of them present ex-vessel debris with Unit 1 and Unit 3 showing evidences of undergoing MCCI. Uncertainties have been identified in particular on the time and magnitude of events such as corium relocation in RPV and into cavity floor, RPV and PCV rupture events. Main uncertainties resulting from the project are the large and continuous MCCI progression predicted by basically all the SA codes and the leak pathways from RPV to PCV and PCV to reactor building and environment. The BSAF project represents a pioneering exercise which has set the basis and provided lessons learned not only for code improvement but also for the development of new related projects to investigate in detail further aspects of the Fukushima Daiichi accident.
Pellegrini, M.*; Herranz, L.*; Sonnenkalb, M.*; Lind, T.*; 丸山 結; Gauntt, R.*; Bixler, N.*; Morreale, A.*; Dolganov, K.*; Sevon, T.*; et al.
Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.1147 - 1162, 2019/08
The OECD/NEA Benchmark Study at the Accident of the Fukushima Daiichi NPS project (BSAF) has started in 2012 until 2018 as one of the earliest responses to the accident at Fukushima Daiichi NPS. The project addressed the investigation of the accident at Units 1, 2 and 3 by severe accident (SA) codes focusing on thermal-hydraulics, core relocation, molten core/concrete interaction (MCCI) and fission products release and transport. The objectives of BSAF were to make up plausible scenarios based primarily on SA forensic analysis, support the decommissioning and inform SA codes modeling. The analysis and comparison among the institutes have brought up vital insights regarding the accident progression identifying periods of core meltdown and relocation, reactor vessel (RV) and primary containment vessel (PCV) leakage/failure through the comparison of pressure, water level and CAMS measurement. The combination of code results and inspections has provided a picture of the current state of the debris distribution and plant state. All units present a large relocation of core materials and all of them present ex-vessel debris with units 1 and 3 showing evidences of undergoing MCCI. Uncertainties have been identified in particular on the time and magnitude of events such as corium relocation in RV and into cavity floor, RV and PCV rupture events. Main uncertainties resulting from the project are the large and continuous MCCI progression predicted by basically all the SA codes and the leak pathways from RV to PCV and PCV to reactor building and environment. The BSAF project represents a pioneering exercise which has set the basis and provided lessons learned not only for code improvement but also for the development of new related projects to investigate in details further aspects of the Fukushima Daiichi NPS accident.
