JAXA Repository / AIREX 未来へ続く、宙(そら)への英知
タイトルシビアアクシデント発生時におけるBWRプラント挙動の基礎的研究 (2): (給水系LOCA+ECCS注入失敗)事故と(SBO+SRV開固着)事故
その他のタイトルBasic Study on BWR Plant Behavior under the Condition of Severe Accident (2)
著者(日)尾崎, 禎彦; 上田, 将正; 佐々木, 一
著者(英)Ozaki, Yoshihiko; Ueda, Masataka; Sasaki, Hajime
著者所属(日)福井工業大学; 福井工業大学; 福井工業大学
著者所属(英)Fukui University of Technology; Fukui University of Technology; Fukui University of Technology
発行日2016-06-30
発行機関など福井工業大学
Fukui University of Technology
刊行物名福井工業大学研究紀要
Memoirs of Fukui University of Technology
46
開始ページ148
終了ページ159
刊行年月日2016-06-30
言語jpn
eng
抄録In this paper, we report on the results using the BWR plant simulator about the plant behavior under the condition of the two types of severe accidents that LOCA occurs but ECCS fails the water irrigation into the reactor core and SBO occurs and at the same time the reclosed failure of SRV occurs. The simulation experiments were carried out for the cases that LOCA has occurred in the main feed-water piping. As for the results about the relationship between the LOCA area and the time from LOCA occurs until the fuel temperature rise start, the effect that RCIC operated was extremely big for small and middle LOCA area. In the case of main feed-water system LOCA, the core water level suddenly decreased for large LOCA of 2000cm2 area, however, if the irrigation into the reactor core was carried out 30min after LOCA occurrence, the core had little damage. In addition, the H2 concentration in the containment vessel did not exceed both limits of H2 explosion nor detonation. The pressure of the containment vessel was around 3kg/cm2 of design value, so the soundness of the containment vessel was confirmed. On the other hand, for the accident of SBO with reclosed failure of SRV, it has been shown that the accidents continue to progress rapidly as compared with the case of normally operating of SRV. Because SRV has the function that keep the inside pressure of reactor core by repeating opened and closed in response of the inside pressure and prevent the decrease of water level inside reactor core. However, if the irrigation into the reactor core was carried out 30min after SBO occurrence, the core had little damage and also the H2 concentration in the containment vessel did not exceed limits of H2 explosion. Further, as for the accident of reclosed failure of SRV, it has been shown that there are very good correspondence with the simulation results of main steam piping LOCA of area 180cm2 corresponding to the inlet cross-sectional area SRV installed on the piping. Therefore, the accident of reclosed failure has been also shown that can be regarded as small LOCA accidents of main steam piping.
内容記述形態: カラー図版あり
形態: CD-ROM1枚
Physical characteristics: Original contains color illustrations
Note: One CD-ROM
キーワードNuclear Power Plant; Safety Assessment; Severe Accident; Severe Accident Management; Plant Behavior in Severe Accident; BWR Plant Simulator
資料種別Departmental Bulletin Paper
NASA分類Nuclear Physics
ISSN1884-4456
NCIDAA12450746
SHI-NOAA1640177010
URIhttps://repository.exst.jaxa.jp/dspace/handle/a-is/575051


このリポジトリに保管されているアイテムは、他に指定されている場合を除き、著作権により保護されています。