Korea Atomic Energy Research Institute

Seo Yoon Jung

Tae Wan Kim

Young In Kim

Keung Koo Kim

Young Soo Kim

Ju Hyeon Yoon

Young Min Bae

Jae Joo Ha

Soo Jai Shin

Hun Sik Han

Joo Hyung Moon

Cheon Tae Park

Kyung Jun Kang

Han Ok Kang

Jong Wook Kim

Seung Yeob Ryu

Jae Seon Lee

Disclosed are an in-vessel control rod drive mechanism and a nuclear reactor with the same. The in-vessel control rod drive mechanism includes a control rod drive mechanism for regulating and a control rod drive mechanism for shutdown provided at an upper or lower space of a reactor core to insert or withdraw a regulating rod and a shutdown rod into/from the reactor core based on an operation state of the nuclear reactor, wherein the control rod drive mechanism for regulating and the control rod drive mechanism for shutdown are alternately arranged in the vertical direction. Therefore, a space of containment can be minimized due to the installation of the in-vessel control rod drive mechanism, and thus a rod ejection accident can be prevented, and a loss-of-coolant accident can be reduced.

In-vessel control rod drive mechanism and nuclear reactor with the same

The present invention relates to a passive heat removal system which circulates cooling fluid to a steam generator via a main water supply line connected to the lower inlet of the steam generator, and a main steam pipe connected to the top outlet of the steam generator, to remove sensible heat of a nuclear reactor coolant system and residual heat of a core. The heat removal system comprises supplementary equipment for receiving surplus cooling fluid or for supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range. The supplementary equipment comprises: a supplementary tank, installed at a height between the lower inlet and the top outlet of the steam generator; a first connection pipe, connected to the main steam pipe and the supplementary tank; and a second connection pipe, connected to the supplementary tank and the main water supply pipe.

Passive heat removal system for nuclear power plant

Growing community of inventors

Daejeon, South Korea

Seo Yoon Jung