Preliminary investigation on improvement of FP management during BWR severe accident with MELCOR-2.2

Kento Matsubara, Akifumi Yamaji, Xin Li, Daisuke Fujiwara, Hiroshi Shirai, Takumi Noujuu

研究成果: Conference contribution

抄録

According to the current Boiling Water Reactor (BWR) accident management procedure, the Reactor Pressure Vessel (RPV) is not depressurized until the core water level has decreased to a predetermined threshold level (e.g., 10% of the active fuel length from the bottom of the active fuel (BAF)) when the backup low pressure water injection is unavailable. In the meantime, significant Fission Products (FPs) may be released due to core degradation. In such case, excessive FP deposition on the RPV dome may lead to heat up and failure of the top flange sealing of the Primary Containment Vessel (PCV) due to radiation heat. For BWR4/Mark-I TQUV event, the relationship between the different depressurization timings and FP release and depositions (represented by CsI and CsOH) on RPV (especially, steam dryer and RPV dome), D/W, W/W have been highlighted with MELCOR-2.2 analyses. Overall, it may be understood that the later the depressurization timing, the later the RPV failure timing, but the larger the amount of FP released to RPV. The remaining FP not trapped by water pool were mostly deposited on the RPV steam dryer. Clear correlation between the FP deposition amount on the steam dryer and its temperature could be confirmed. However, more investigations may be necessary to reveal what determines the RPV dome temperature, which seemed to have limited influence on the D/W head temperature profile.

本文言語English
ホスト出版物のタイトルNuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors
出版社American Society of Mechanical Engineers (ASME)
ISBN(印刷版)9784888982566
DOI
出版ステータスPublished - 2020
イベント2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference - Virtual, Online
継続期間: 2020 4 42020 4 5

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
2

Conference

Conference2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
CityVirtual, Online
Period20/4/420/4/5

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

フィンガープリント

「Preliminary investigation on improvement of FP management during BWR severe accident with MELCOR-2.2」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル