Hitachi, Ltd.

Hitachi Engineering Co., Ltd.

Hitachi-ge Nuclear Energy, Ltd.

Kimiko Isono

Shin Hasegawa

Toichi Shida

Naoshi Tanikawa

Hitoshi Sakuma

Tetsuya Miyakawa

In the present invention, a reactor power control apparatus of a natural circulation reactor comprises a power control apparatus for controlling reactor power and a pressure control apparatus for controlling reactor pressure. A power adjustment demand signal Sis input from the power control apparatus into the pressure control apparatus. The pressure control apparatus controls degree of opening of a inlet port steam control valve provided in a moisture separation heater that is connected to a low-pressure turbine, based on the power adjustment demand signal S. A reactor power control apparatus of the natural circulation reactor can suppress reactor power variation and obtain stable power.

Reactor power control apparatus of natural circulation reactor, generation system of natural circulation reactor and method for controlling reactor power of natural circulation reactor

A reactor core coolant flow rate control system for a BWR type nuclear power plant in which electric power is generated by a turbine-driven generator driven by a steam turbine rotating under the work of a main steam generated from a cooling water recirculated through a boiling water reactor includes an internal pump driving unit comprised of an electric motor driven by an electric power generated by the turbine-driven generator, a fluid coupling for transmitting an output torque of the electric motor and a variable-frequency generator whose rotation number is changed in accordance with the torque transmitted by way of the fluid coupling, a fluid coupling control signal generating unit for generating a fluid coupling control signal for the fluid coupling in response to at least one of deviation in a load and a rotation speed of the turbine-driven generator and deviation in a rotation speed of the internal pumps, and a plurality of internal pumps for recirculating the cooling water. Each of the internal pumps is connected to the variable-frequency generator of the internal pump driving unit and driven by an output power of the variable-frequency generator. Rotation number of the internal pump changes in dependence on the rotation number of the variable-frequency generator. The fluid coupling changes a transmission efficiency for the torque transmitted to the variable-frequency generator from the driving motor in response to the fluid coupling control signal.

Reactor core coolant flow rate control system for a BWR type nuclear

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Hitachi, Japan

Kimiko Isono