Hitachi-ge Nuclear Energy, Ltd.

Hitachi, Ltd.

Kazuaki Kito

Hiroshi Nakano

Motoo Aoyama

Tomohiko Ikegawa

Masao Chaki

Yukinori Katagiri

Masaru Sekihara

Akinori Tamura

Yoshihiko Ishii

Naoyuki Ishida

Mamoru Kamoshida

Tsuneyuki Hashimoto

Katsuhito Takahashi

Takahisa Matsuzaki

Sohei Fukui

Ryou Ishibashi

Masataka Hidaka

Toshinori Kawamura

Tetsushi Hino

Koji Ando

Kenichi Katono

Yuji Hosokawa

Katsuki Hamada

Masayoshi Matsuura

Masaya Ohtsuka

Motoki Nakane

Provided is a power supply system that contributes to stabilization of a power system, and the like. A power supply system includes a control unit that uses at least a part of generated power of a photovoltaic power plant and a wind power plant that generate power with asynchronous power supplies as in-plant power to be used for a motor and another load during normal operation of a nuclear power plant that generates power with a main generator that is a synchronous power supply. The control unit uses at least a part of the generated power of the photovoltaic power plant and the wind power plant as the in-plant power during the normal operation of the nuclear power plant to reduce an in-plant ratio in the nuclear power plant.

Power supply system and power supply method

In view of above problems, an object of the invention is to provide a primary containment vessel venting system having a structure capable of continuously discharging vapor in a primary containment vessel out of the system and continuously reducing pressure of the primary containment vessel without discharging radioactive noble gases to the outside of the containment vessel and without using an enclosing vessel or a power source. In order to achieve the above object, an nuclear power plant of the invention includes a primary containment vessel which includes a reactor pressure vessel, a radioactive substance separation apparatus which is disposed inside the primary containment vessel and through which the radioactive noble gases do not permeate but vapor permeates, a vent pipe which is connected to the radioactive substance separation apparatus, and an exhaust tower which is connected to the vent pipe and discharges a gas, from which a radioactive substance is removed, to the outside.

Nuclear power plant

When a power source is lost after an operation stop of a nuclear power plant, a first open/close valve is opened via a first battery at an early stage and steam in a reactor pressure vessel (RPV) is condensed in a suppression pool. The heat of the water in the suppression pool is transmitted to a cooling water pool located below inner space between first and second reactor containment vessels surrounding the RPV. A second open/close valve is opened via a second battery at the early stage and cooling water in a tank is injected into the RPV. After the early stage, a third open/close valve is opened via a third battery, and a cooling medium becomes steam by an evaporator in the RPV, the steam being condensed by a condenser disposed in the inner space to become a liquid of the cooling medium and is returned to the evaporator.

An atomic power plant is provided including a primary containment vessel (PCV), a reactor pressure vessel (RPV), a main steam line, two steam safety relief valves (SRVs), a pressure suppression pool (S/P), an SRV exhaust pipewhich is connected to a quencher, a temperature measuring instrumentwhich measures a temperature inside the quencher, an SRV controllerwhich controls opening and closing of the SRVs. After a lapse of predetermined time from when the SRVis opened, in a case where it is determined that a temperature detected by the temperature measuring instrumentis equal to or smaller than a predetermined threshold value, the SRV controllercauses the SRVto which the temperature measuring instrumentdetecting the temperature leads, to be closed and to be prohibited from being opened.

Nuclear power plant that can automatically close a steam safety relief valve upon determination of exhaust pipe leakage

A heat exchanger has a tubular structure inside of which a medium flows. The heat exchanger includes a liquid film removal structure and a liquid film flowing-down assistance structure. The liquid film removal structure is joined to the tubular structure. The liquid film flowing-down assistance structure is coupled directly to the liquid film removal structure and is arranged between the tubular structure and an adjacent tubular structure and in parallel to the tubular structure.

Heat exchanger and heat transfer tube of the heat exchanger

The invention includes a heat exchanger provided at a position higher than a primary containment vessel; a condensate storage tank disposed below the heat exchanger and above an upper end of a reactor core placed in a reactor pressure vessel; a non-condensate gas discharge line connected to an upper section of the condensate storage tank and to a suppression pool; a second condensate discharge line connected to a position below that section of the condensate storage tank to which a first end of the non-condensate gas discharge line is connected, and to the suppression pool; and a condensate return line connected to a position below that section of the condensate storage tank to which a first end of the second condensate discharge line is connected, and to a side portion of the reactor pressure vessel, the side portion being above the upper end of the core.

Passive residual heat removal system and nuclear power plant equipment

Growing community of inventors

Tokyo, Japan

Kazuaki Kito