EVALUATION OF EFFECT OF DEPRESSURIZATION TIMING ON THE THERMAL LOAD TO PRIMARY CONTAINMENT VESSEL DURING SEVERE ACCIDENT AT BWR

Taisei Matsumoto, Akifumi Yamaji, Daisuke Fujiwara

研究成果

抄録

According to accident of a Boiling Water Reactor (BWR), the operators generally do not depressurize the Reactor Pressure Vessel (RPV) until low-pressure core injection systems are recovered. However, when the core water level decreases below a certain limit, the RPV is depressurized to prevent the RPV failure at high pressure, which may lead to failure of the Primary Containment Vessel (PCV) by direct heating of the ejected melt. In such a case, if recovery of the core cooling cannot be expected, earlier depressurization may be preferable from the viewpoint of reducing thermal load on PCV, because it may effectively reduce the amount of fission product (FP) aerosol deposition on the RPV dome and reduce the risk of PCV top head heating via convective and radiative heat transfers from the RPV dome. However, significance of such risk is not evident as the steam dryer and separator may hinder direct aerosol deposition on the RPV dome and the RPV dome is thermally insulated. Moreover, the narrow space between the RPV dome and the PCV top head may hinder convective heat transfer. In this study, sensitivity analyses have been carried out using MELCOR-2.2 to support such understanding.

本文言語English
ホスト出版物のタイトルMitigation Strategies for Beyond Design Basis Events
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
11

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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