Hitachi, Ltd.

Hitachi Engineering Co., Ltd.

Other

Tetsuo Horiuchi

Kenji Tominaga

Shozo Yamanari

Tsuyoshi Niino

Toshihiko Sugisaki

Kumiaki Moriya

Tooru Takahashi

Minoru Miki

Kanehiro Ochiai

Shouichirou Kinoshita

Minoru Akita

Takashi Nakayama

Yuichi Uchiyama

Hiroshi Goto

Osamu Yokomizo

Tasuku Shimizu

Naoyuki Yamada

Yoshiyuki Kataoka

Isao Sumida

Masanori Naitoh

Michio Murase

Masataka Hidaka

Hiroaki Suzuki

Kunio Hasegawa

Masaki Matsumoto

Mamoru Morita

Tohru Fukui

Satoshi Miura

Toyoharu Yasuno

Kenji Moriya

Akihiko Shiozawa

Kazuo Kage

Ryuji Kubota

Shouichiro Kinoshita

Hideo Morishima

Hideo Ogasawara

Syozo Yamanari

Hisao Ito

An energy supply system includes at least two devices selected from a device for generating electric power, a device for heating a heat conveying medium to an atmospheric temperature or higher and a device for cooling a heat conveying medium to the atmospheric temperature or lower; a device for supplying at least two selected from electric power, heat of atmospheric temperature or higher and cold of atmospheric temperature or lower to a plurality of customers; a device for measuring supply quantities of electric power, heat and cold, supplied to the plurality of customers; a device for calculating usage charges for electric power, heat and cold, consumed by each of the customers on the basis of the supply quantities; and a device for settling the usage charges. One enterprise entity manages these activities.

Energy supply system and operation method thereof

A reactor containment facility having a reactor pressure vessel containing a core; a dry well in which the reactor pressure vessel is arranged; a suppression chamber holding suppression-pool water and forming above the suppression-pool water a wet well; and a plurality of vent pipes allowing the dry well to communicate with the suppression-pool water; a steel wall which is in contact with the suppression-pool water of the suppression chamber and which surrounds at least the pool water so as to form a containment vessel which houses the dry well and the suppression chamber; and an outer peripheral pool containing cooling water in contact with the outer peripheral surface of the steel wall. The facility further includes: a dividing structure for dividing the wet well of the suppression chamber into a first space which is in contact with the water surface of the suppression-pool water and a second space which is not in contact therewith; a first passage which allows the first space to communicate with the second space and which has an area smaller than that of the dividing device; and a cooling device for keeping the second space at a temperature lower than that of the first space.

Reactor containment facilities

A nuclear reactor facility including a primary containment vessel, a reactor pressure vessel installed in the primary containment vessel and accommodating a reactor core in a lower part thereof, and a vertical cylindrical wall disposed in a lower part of the primary containment vessel around and spaced from the reactor pressure vessel so as to delimit an annular space therebetween. The vertical cylindrical wall has an upper end disposed at a position higher than an upper end of the reactor core and a diaphragm extends substantially horizontally between the upper end of the vertical cylindrical wall and an inner wall of the primary containment vessel for cooperating with the vertical cylindrical wall to separate a space in the primary containment vessel around the reactor pressure vessel into a pressure suppression chamber and a drywell which includes annular space. The pressure suppression chamber accommodates therein a pool of liquid coolant wherein a level of the liquid coolant of the pool is higher than the upper end of the reactor core. The vertical cylindrical wall has a plurality of vent passages having an upper part at the upper end of the vertical cylindrical wall and exposed to the drywell and a lower part exposed to the pool of the liquid coolant in the pressure suppression chamber. A submergence line and a channel member are also provided.

Nuclear power facilities

A container-outer-periphery pool in which water is stored is provided between a primary containment vessel and a reactor building, and outside of a pressure suppression pool. Consequently, the natural heat transfer capabilities of reactor facilities is enhanced, and the inherent safety of the reactor facilities is improved.

Two systems of low-pressure core spray appratuses have coolers, and are adapted to supply cooling water to a core spray header provided in a core-surrounding cylindrical shroud in a reactor pressure vessel. Two systems of high-pressure core flooding apparatuses and one system of high-pressure coolant injection apparatus are adapted to supply the cooling water to a region formed between the shroud and reactor pressure vessel. The elevation of the openings, which are in the reactor pressure vessel, of the high-pressure core flooding apparatuses and high-pressure coolant injection apparatus are higher than that of the core spray header. A pipe for returning the cooling water in the reactor pressure vessel to the above-mentioned coolers is connected to either the portion of the interior of the reactor pressure vesssel which is below the core or the portion of the interior of the reactor pressure vessel which is between the walls of the shroud and reactor pressure vessel. The above-mentioned pipe is provided therein with a valve which is adapted to be closed when the nuclear reactor stops being operated in an emergency in which the breakage of a pipe occurs, and to be opened when the nuclear reactor is stopped under normal conditions.

Emergency core cooling apparatus

Piping of a nuclear reactor containment vessel comprises pipes passing through the containment vessel and, extending to the outside of the containment vessel, outer shut-off valves each provided at a portion of the pipe which is located at the outside of the containment vessel for closing the pipe and isolating vessels for covering at least outer surfaces of welded portions of the pipes each being located between an outer wall surface of the containment vessel and a portion including the outer shut-off valve and for isolating the covered portions of the pipes from atmosphere.

Piping of nuclear reactor containment vessel

A containment vessel for a nuclear reactor having a dry well for mounting therein a pressure vessel for containing the nuclear reactor, a pressure suppressing chamber having a pool of coolant therein, and a vent pipe device for releasing therethrough into the pool of coolant within the pressure suppressing chamber steam which will be produced as a result of the occurrence of an accident and escape into the dry well. The vent pipe device includes a plurality of vent pipe members inserted in the pool of coolant within the pressure suppressing chamber and each having at least one exhaust port opening in the coolant. The vent pipe members are divided into a plurality of groups in such a manner that the vent pipe members of different groups differ from one another in the length of submerged portions of the vent pipe members interposed between the liquid of the coolant within the pressure suppressing chamber and the exhaust ports of the vent pipe members.

Containment vessel for a nuclear reactor

A device having a tubular body of an increased diameter closed at its bottom and connected at its top to the lower end of a vent pipe in such a state that the tubular body is immersed in a water pool. The tubular body is formed in its side wall with a multitude of openings for venting steam therethrough to the water pool to condense the same.

Vent exit device for condensing steam

Fuel assemblies forming the core of a nuclear reactor each include an open-ended tubular channel, upper and lower tie plates formed therein with a multitude of through holes and arranged in the vicinity of upper and lower ends of the tubular channel respectively, and elongated fuel elements located parallel to one another and extending between the upper and lower tie plates. The channel of each fuel assembly is formed in its walls with openings which are disposed below the upper tie plate and above the upper end edge of the fuel of each fuel element.

Fuel assembly for a nuclear reactor

Growing community of inventors

Hitachi, Japan

Tetsuo Horiuchi