抄録
This paper deals with liquid film dryout and rewetting behavior under BWR (Boiling Water Reactor) transient condition. The rewetting behavior has not been fully clarified. Therefore, the transient BT (Boiling Transition) tests were performed using a simulated BWR 4x4 rod bundle which many thermocouples were installed along one of the heater rod in order to clarify the re-wetting behavior. The following results were obtained; (1) The BT occurs initially just upstream of the spacer. The location of BT then propagates upstream, and finally rewetting occurs upstream between adjacent spacers. (2) The liquid film front exists between spacers. (3) Rewetting propagation velocity decreases, as wall superheat increases.
| 本文言語 | English |
|---|---|
| ページ（範囲） | 510-516 |
| ページ数 | 7 |
| ジャーナル | Transactions of the Atomic Energy Society of Japan |
| 巻 | 2 |
| 号 | 4 |
| DOI | |
| 出版ステータス | Published - 2003 |
| 外部発表 | はい |
ASJC Scopus subject areas
- 原子力エネルギーおよび原子力工学
- 安全性、リスク、信頼性、品質管理