Kabushiki Kaisha Toshiba

The Tokyo Electric Power Company, Incorporated

Makoto Yasuoka

Tadashi Narabayashi

Mikihide Nakamaru

Yutaka Asanuma

Naotaka Oda

Michitsugu Mori

Shinichi Morooka

Kenji Kumagai

Shuichi Ohmori

Miyuki Akiba

A feed water heating system for heating a feed water for a power-generating plant having a steam turbine, a condenser and a steam generator, comprises: a steam injector unit for receiving a plurality of bled steams having different pressures extracted from the steam turbine and an effluent water discharged from the condenser to mix the effluent water with the plurality of bled steams to raise the temperature and pressure of a mixture of the effluent water with the plurality of bled steams to deaerate and discharge the temperature and pressure raised mixture. The steam injector unit comprises: a multistage steam injector having a plurality of steam injectors connected in series for receiving one of the plurality of bled steams and a feed water to mix the one of the plurality of bled steams with the feed water to raise the temperature and pressure of a mixture of the one of the plurality of bled steams and the feed water to discharge the temperature and pressure raised mixture; a cylindrical container for housing therein the multistage steam injector; and a jet centrifugal deaerator, provided downstream of the multistage steam injector, for receiving a feed water discharged from the multistage steam injector and the bled steams to apply a centrifugal force to the feed water and the bled steams to deaerate the feed water to spatially separate a deaerated feed water from the bled steams to discharge the deaerated feed water.

Feed water heating system for power-generating plant

A separator/injector having an outlet pressure higher than an inlet pressure thereof is introduced instead of the dynamic equipment for a reactor recirculation system that is necessary in the prior art, to achieve both liquid-vapor separation and forced circulation. A jet pump and a recirculation flow-rate control valve are provided in a lower portion of a downcomer portion of a reactor pressure vessel. A shroud head has a double-walled structure, a two-phase liquid-vapor flow that is flowing from a lower portion of the lower shroud head is accelerated by an accelerator nozzle of the separator/injector, and a liquid component of the thus-separated flow is increased in pressure and guided into a jet pump through a space formed between the double shroud heads. Alternatively, a circular cylindrical separator/injector in which the steam nozzle and diffuser are disposed in a helical form in close proximity to the inner wall of a circular tube above the stand pipe could be provided instead of this separator/injector.

Steam separator, nuclear power generation plant, and boiler apparatus

An apparatus for measuring the power of a nuclear reactor having a sensor assembly disposed in a core section inside the nuclear reactor. The sensor assembly includes a cover tube made of metal and press-fitted on the outer surface of a rod-shaped core tube made of metal, a plurality of annular gaps defined between the cover tube and the core tube at different positions spaced from each other in the axial direction of the core tube, a plurality of axial grooves formed in the core tube while opening on the outer surface of the core tube and extending in the axial direction of the core tube, and a plurality of temperature sensors individually guided in the axial grooves and disposed on the core tube. The temperature sensors of the sensor assembly detect temperature distribution in portions of the core tube which face the annular gaps so as to measure the power of the nuclear reactor. By virtue of the above construction, the apparatus can be manufactured easily, has high precision of temperature measurement, and has a sufficiently high reliability for reducing problems such as disconnection and insulation failure.

Apparatus for measuring power of nuclear reactor and method for

Growing community of inventors

Yokohama, Japan

Makoto Yasuoka