Kabushiki Kaisha Toshiba

Hirohide Oikawa

Takashi Sato

Yoshihiro Kojima

Makoto Akinaga

Ryoichi Hamazaki

Kenji Arai

Yuka Suzuki

Mika Tahara

Hisaki Sato

Yasunobu Fujiki

Kazunori Hashimoto

Tomohisa Kurita

Seiichi Yokobori

Hiromasa Yanagisawa

Hideo Nagasaka

According to an embodiment, a pressurized water reactor plant has a primary system which includes: a reactor vessel for housing a reactor core which is cooled by a primary coolant, a single steam generator, a hot leg pipe for connecting the reactor vessel and the steam generator, cold leg pipes, at least two primary coolant pumps, and a pressurizer for pressurizing the primary coolant pressure boundary in which the primary coolant flows. The plant also has: a passive cooling and depressurization system which is a primary depressurization means for equalizing the primary system pressure to the secondary system pressure at the time of a tube rupture accident of the steam generator, and a reactor containment vessel containing the primary system and cooling the primary system by air cooling. Thus, a compact pressurized water rector with high economic efficiency, safety, and reliability can be provided.

Pressurized water reactor plant

A drain sump of a reactor containment vessel having a containment vessel floor down below a reactor pressure vessel, and includes a heat-proof sump cover and two or more drain flow paths. The drain sump is arranged inside the containment vessel floor. The heat-proof sump cover has a thickness, and covers an upper part of the drain sump. The thickness allows a top surface of the sump cover to lie in the same surface as a top surface of the containment vessel floor. The drain flow paths pass through the sump cover in a thickness direction to flow water therethrough and solidify a molten corium therein. The molten corium is produced in the unlikely event of a severe accident.

Drain sump of nuclear reactor containment vessel

Core debris generated during a molten reactor core in a reactor containment vessel penetrating the reactor containment vessel is configured to be caught by a core catcher located beneath the reactor containment vessel which has a main body having first stage cooling water channels and second stage surrounded by cooling fins extending radially. The number of the second stage cooling channels is larger than that of the first stage cooling channels. Cooling water is supplied from a cooling water injection opening and distributed to the first cooling water channels at a distributor. An intermediate header is formed between the first and the second cooling water channels, and the cooling water is distributed to the second cooling water channels uniformly.

Core catcher, manufacturing method thereof, reactor containment vessel and manufacturing method thereof

A boiling water nuclear reactor comprises: a reactor containment vessel including a dry well and a wet well; a vent pipe connecting the dry well and the pressure suppression pool; a gravity-driven water injection pool to hold boric acid aqueous solution; an emergency core water-injection piping system for causing the boric acid aqueous solution in the gravity-driven water injection pool to fall so as to be injected into the reactor pressure vessel in case of reactor accident; a static containment vessel cooling system pool; a static containment vessel cooling system heat exchanger; a dry well connection pipe connecting an upper part of the static containment vessel cooling system heat exchanger and the dry well; and a gas vent pipe for discharging noncondensible gas in the static containment vessel cooling system heat exchanger into the inside of the pressure suppression pool.

Boiling water nuclear reactor and emergency core cooling system of the same

An emergency core cooling system comprises first and second safety divisions for an active emergency core cooling system. Each of the first and second safety divisions is provided with a high-pressure core cooling system and a low-pressure core cooling system, which also acts as a residual heat removal system.

Emergency core cooling system

A reactor containment vessel with a cooling system includes a communication pipe having a valve to be connected to either an emergency condenser or suppression chamber in order to improve cooling performance by removing non-condensable gas from heat exchanger tubes when a main steam line is broken. One open end of the communication pipe is opened and positioned at a low position of the dry well. The valve is constantly closed and actuated to be opened in an abnormal condition of a reactor. When the valve is opened, the communication pipe introduces the non-condensable gas existing in the emergency condenser or suppression chamber to the low area of the dry well due to a density differential between steam and non-condensable gas, thus removing the non-condensable gas from the heat exchanger tubes, and improving the cooling performance of the emergency condenser.

Growing community of inventors

Kanagawa, Japan

Hirohide Oikawa