ESTIMATION OF THE 1F2 CORE THERMAL STATUS DURING THE CORE HEAT-UP PHASE WITH MELCOR-2.2

Shotaro Osako, Xin Li, Akifumi Yamaji

研究成果

抄録

For decommissioning of the Unit 2 of Fukushima Daiichi Nuclear Power Station (1F2), more supportive information is necessary regarding the debris distributions and characteristics as complementary to what has been gained through internal investigations. The current debris status is expected to have been greatly affected by the peak core energy (temperature) during the core heat-up phase, before collapsing (slumping) to the lower plenum of the reactor pressure vessel (RPV), at the time of the accident. In another word, whether the oxidic fuel melted in the core region or not. Such supportive information can be gained through detailed analyses of the plant data and the corresponding accident progression analyses. In this study, accident progression analyses of 1F2 were performed considering uncertainty of the core oxidation and the impact of the leakage from the RPV to the D/W on the estimated core energy with the severe accident analysis code MELCOR-2.2. The best estimate case successfully reproduced RPV and D/W pressure histories and showed that the peak core temperature was about 2700 K. This indicated that large-scale melting of the oxidic fuel in the core region was unlikely in 1F2, although some local oxidic fuel melting may have taken place.

本文言語English
ホスト出版物のタイトルThermal-Hydraulics and Safety Analysis
出版社American Society of Mechanical Engineers (ASME)
ISBN(印刷版)9784888982566
DOI
出版ステータスPublished - 2022
イベント2022 29th International Conference on Nuclear Engineering, ICONE 2022 - Virtual, Online
継続期間: 2022 8月 82022 8月 12

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
7-A

Conference

Conference2022 29th International Conference on Nuclear Engineering, ICONE 2022
CityVirtual, Online
Period22/8/822/8/12

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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