AIREX: A Study on ROSA/LSTF SB-CL-09 test simulating PWR 10% cold leg break LOCA; Loop-seal clearing and 3D core heat-up phenomena

タイトル	A Study on ROSA/LSTF SB-CL-09 test simulating PWR 10% cold leg break LOCA; Loop-seal clearing and 3D core heat-up phenomena
その他のタイトル	PWR低温側配管10%破断LOCAを模擬するROSA/LSTF SB-CL-09実験の考察; ループシールクリアリングと3次元炉心過熱現象
DOI	10.11484/jaea-research-2008-087
本文（外部サイト）	http://jolissrch-inter.tokai-sc.jaea.go.jp/pdfdata/JAEA-Research-2008-087.pdf
参考URL	http://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?5015313
著者（日）	鈴木光弘; 中村秀夫
発行日	2008-10
発行機関など	JAEA
刊行物名	JAEA-Research 2008-087
開始ページ	1
終了ページ	148
刊行年月日	2008-10
言語	en
内容記述	This report presents major results observed in LOCA test (SB-CL-09) conducted at the ROSA/LSTF test facility simulating 10% cold leg break in a 4-loop Westinghouse-type PWR. Following are found in this test with an assumption of high pressure injection system. (1) The relatively large break size resulted in pressure inverse within 2 minutes between the primary and steam generator secondary sides. (2) During a loop-seal clearing (LSC) process started at about 1 minutes after the break, the core water level was suppressed to almost lower end and then it recovered to the middle core height. The water level remained at the middle height was due to remained water levels in the SG U-tube inlet sides which were higher than their outlet sides. (3) Significant core heat-up was observed above the water level at the middle height and core power was tripped off at 111s. (4) The effects of fall-back water from the intact loop hot leg was observed by the local core cooling. 著者所属: 日本原子力研究開発機構(JAEA)
資料種別	Technical Report
URI	https://repository.exst.jaxa.jp/dspace/handle/a-is/617084