Kabushiki Kaisha Toshiba

Hisaki Sato

Takashi Sato

Kazunori Hashimoto

Yasunobu Fujiki

Junichiro Otonari

Ken Uchida

Satoru Abe

Masanobu Watanabe

Hirohide Oikawa

Makoto Akinaga

Chikako Iwaki

Tetsuzo Yamamoto

Takuya Miyagawa

Ken Okuda

Masanori Ino

Naoko Matsunaga

Tatsumi Ikeda

Kiichi Ito

Fujiki Yasunobu

A containment vessel for containing a reactor pressure vessel, a reactor core, and a steam generator of a pressurized water reactor includes a main body equipped with a polar crane, a diaphragm set above the polar crane that partitions the main body, before and after a loss-of-coolant accident (LOCA), into an upper vessel including a dome part having an open space and a lower vessel isolated from the upper vessel, a pressure suppression chamber including a suppression pool that stores water and a gas phase in communication with the open space, a LOCA vent pipe connecting the suppression pool to the lower vessel, and a vacuum breaker that equalizes pressure by allowing gas flow from the upper to the lower vessel when a pressure difference between the upper and lower vessels exceeds a preset value. The lower vessel contains all equipment and piping constituting a reactor pressure boundary.

Containment vessel and nuclear power plant therewith

The pressurized water reactor according an embodiment comprises: a cylindrical reactor pressure vessel () to which inlet nozzles are connected; fuel assemblies which are contained within the reactor pressure vessel (); a cylindrical reactor core barrel () which surrounds the fuel assemblies and forms an annular downcomer () between the reactor core barrel () and the inner surface of the reactor pressure vessel (); and radial supports. The radial supports are supports which are arranged below the downcomer () at intervals in the circumferential direction, each has vertical flow path formed therein, and position the reactor core barrel () and the reactor pressure vessel (). The radial supports each has, for example, a flow path-equipped radial keys () and a key groove member ().

Pressurized water reactor

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 passive cooling and depressurization system for a pressurized water nuclear plant is provided with a cooling water pool, a steam supply piping, a heat exchanger, a steam supply valve, a coolant return pipe and an outlet valve. The steam supply piping extends from the gas phase of the pressurizer. The heat exchanger exchanges heat between water stored in the cooling water pool and steam flowing through the steam supply piping. The steam supply valve is equipped on the steam supply piping. The coolant return pipe extends from the heat exchanger to a liquid phase of the reactor pressure boundary. The outlet valve is equipped on the coolant return pipe.

Passive cooling and depressurization system and pressurized water nuclear power plant

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Kanagawa, Japan

Hisaki Sato