ライブラリ登録: Guest
ホーム アーカイブ 役員 今後の会合 American Society of Thermal and Fluids Engineering
Second Thermal and Fluids Engineering  Conference

ISSN: 2379-1748
ISBN: 978-1-56700-430-4

EXPERIMENTAL STUDY ON THE BLOWDOWN LOAD DURING THE STEAM GENERATOR STEAM LINE BREAK ACCIDENT IN THE EVOLUTIONARY PRESSURIZED WATER REACTOR

Kyoung-Ho Kang
Korea Atomic Energy Research Institute, Daedeok-Daero 989 Beon-Gil 111, Yuseong-Gu, Daejeon, KOREA

Yu-Sun Park
Korea Atomic Energy Research Institute, Daedeok-Daero 989 Beon-Gil 111, Yuseong-Gu, Daejeon, KOREA

Jongrok Kim
Korea Atomic Energy Research Institute, 111 Daedeok-daero 989Beon-gil Yuseong-gu Daejeon, Republic of Korea.

Byoung-Uhn Bae
Korea Atomic Energy Research Institute, Daedeok-Daero 989 Beon-Gil 111, Yuseong-Gu, Daejeon, KOREA

Nam-Hyun Choi
Korea Atomic Energy Research Institute, Daedeok-Daero 989 Beon-Gil 111, Yuseong-Gu, Daejeon, KOREA

Ki-Yong Choi
Korea Atomic Energy Research Institute, Daejeon, Korea

DOI: 10.1615/TFEC2017.ist.017820
pages 1821-1824

要約

A sudden break of a steam generator steam line can induce an anticipated hydrodynamic load on the internal structures of a steam generator. From a structural integrity point of view, a precise prediction on the hydrodynamic load during the steam generator feedwater line break is important for a safety analysis of nuclear power plant. Integral effect tests using the ATLAS facility were performed to obtain the thermal-hydraulic parameters such as dynamic and static pressures, local temperatures, and flow rates during a steam line break of a steam generator. Break of a steam line was simulated using a double rupture disc assembly for satisfying the requirement for the break opening time around a few milliseconds. In the present work, estimated break opening time was less than 1.4 ms and broken areas were 100 % of the steam line, respectively. The maximum dynamic pressure was obtained at the steam outlet nozzle end where it was closest to the break spool of the steam line. After the break opening of the steam line, propagation of the pressure wave along the flow line inside the steam generator was not clearly observed in the present tests. Especially, the variations of dynamic pressures measured inside the steam dome and the outlet region of steam separator were trivial. This result indicates that the dynamic pressure wave was dampened during the propagation process inside the steam generator in case of the steam line break accident. From a qualitative point of view, it could be found that the steam line break accident does not produce significant hydrodynamic load propagated inside the steam generator.

購入する $20.00 Check subscription 出版倫理 私の図書館員へ推薦 このページをブックマークする