Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants

• Published in: Nuclear engineering and technology Vol. 53; no. 12; pp. 4003 - 4013
• Main Authors: Song, Yong Jae, Lim, Dong Seok, Heo, Min Beom, Kim, Beom Kyu, Lee, Doo Yong, Jo, Daeseong
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.12.2021; Elsevier
• Subjects: Debris; Fiberglass; GSI-191; Insulation; Licensing issue; Nuclear power plants; Insulation; Licensing issue; Nuclear power plants; Debris; Fiberglass; GSI-191
• ISSN: 1738-5733
• DOI: 10.1016/j.net.2021.07.003

During the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), water is supplied from the containment sump to the reactor coolant system (RCS) by the flooded sump water to the Reactor Vessel (RV) through the broken pipes. As part of the technical efforts for resolving GSI-191 [( Reid and Crytzer, May. 2007) 1, consideration is needed for the consequences of debris penetrating the sump screen and propagating downstream into the RV. Injection of debris (fiberglass) into the RV during the LTC recirculation phase needs special attention to assure that reactor core cooling is maintained. The point of concern is the potential for debris to adversely affect the reactor core flow paths or heat transfer [2]. However, all the experiments for proving the coolability of RV have been done with the assumption of the most of debris would be transferred to the RV and the bottom nozzle of the FAs. The purpose of the tests is to quantify the amount of the debris that would be accumulated at the lower plenum and the debris that passes through the FAs since non-conservatism of other researches assumptions that have been used in the past experimental or analytical programs.