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    • 42. 发明专利
    • ATOMIC REACTOR
    • JP2013253830A
    • 2013-12-19
    • JP2012128840
    • 2012-06-06
    • MITSUBISHI HEAVY IND LTD
    • TAKASHIMA RISAKOSHIMIZU AKIRA
    • G21C15/18G21D3/04G21D7/04
    • PROBLEM TO BE SOLVED: To provide an atomic reactor capable of stably removing decay heat by a decay heat removal system even when the power supply is totally turned off.SOLUTION: A decay heat removal system for removing the decay heat generated when the reactor is stopped by exchanging heat between a reactor coolant circulating inside a reactor vessel and the atmospheric air via a coolant medium circulating in a closed circuit in natural convection includes: a chimney-shaped air flow passage 30 provided with an air inlet port 31 and an air discharge port 32 to circulate the air in natural convection; a decay heat removal exchanger provided inside the core coolant for exchanging heat between the coolant medium and the core coolant; an air cooler 40 provided in the air passage 30 for exchanging heat between the coolant medium and the air; an air flow controller 50 having an inlet dumper 51 and a discharge dumper 52 for adjusting the amount of an air flow passing through the air cooler 40 provided in the air passage 30; and a thermoelectric generation device 60 provided on the outer wall of the air passage 30 for generating the power based on a temperature difference between the outside and the inside of the flow passage so as to become a power supply source of the air flow controller 50 when the power is totally turned off.
    • 43. 发明专利
    • Renewed abwr adapted to combined power generation
    • 再生ABWR适用于组合发电
    • JP2009115571A
    • 2009-05-28
    • JP2007288046
    • 2007-11-06
    • Toshihisa Shirakawa白川 利久
    • SHIRAKAWA TOSHIHISA
    • G21C5/22G21C1/08G21C15/02G21D7/04
    • Y02E30/31Y02E30/38
    • PROBLEM TO BE SOLVED: To improve power generation efficiency by renewing a current advanced boiling water reactor (ABWR) by modifying it not on a large scale.
      SOLUTION: Further power generation through the agency of a steam turbine (41) with high-pressure saturated steam (23) produced by cooling high-pressure superheated steam (24) during a power generation process in a newly laid electrothermal semiconductor (100) after generating power with the electrothermal semiconductor (100) by producing the high-pressure superheated steam (24) through some modification of a licensed ABWR leads to combined power generation to improve the power generation efficiency.
      COPYRIGHT: (C)2009,JPO&INPIT
    • 要解决的问题:通过更新现有的先进沸水反应堆(ABWR),通过不大规模改造来提高发电效率。 解决方案:通过在新生电热半导体的发电过程中通过冷却高压过热蒸汽(24)产生的具有高压饱和蒸汽(23)的蒸汽轮机(41)的进一步发电( 100)通过利用许可的ABWR的一些修改来生产高压过热蒸汽(24),通过电热半导体(100)发电来实现组合发电以提高发电效率。 版权所有(C)2009,JPO&INPIT
    • 44. 发明专利
    • REFLECTOR CONTROLLING TYPE REACTOR
    • JP2000180576A
    • 2000-06-30
    • JP36276898
    • 1998-12-21
    • TOSHIBA CORP
    • KONDO NARUHITOMATSUMIYA HISATOIIDA NORIHIKO
    • H01L35/32G21C1/00G21C1/02G21C1/32G21C3/40G21C7/28G21D7/04
    • PROBLEM TO BE SOLVED: To improve economy, simplify the system and facilitate maintenance, etc., by utilizing heat and flow of primary coolant, directly generating steam or electricity in the reactor itself and reducing or eliminating the structure of a multitude of heat conduction pipes and the like conventionally required. SOLUTION: Inside a reactor vessel 22, a core 23, a neutron shield body 26 surrounding the core 23, a movable neutron reflector 24 arranged between the core 23 and the neutron shield body 26 are provided. By moving the neutron shield body 26, leakage of neutron from the core 23 is controlled and reactivity of the core 23 is controlled. The secondary coolant 31 introduced in the reactor vessel 22 is heat-exchanged with primary coolant 21. At the introduction part of the secondary coolant 31 on the reactor vessel 22, paths wherein the primary coolant 21 and the secondary coolant 31 flow side by side in high and low temperature sides of a thermoelectric element module 42 are provided. A thermoelectric generator 28 generating power based on the temperature difference by exchanging heat between primary and secondary coolant 21 and 31 flowing in each path is provided.
    • 46. 发明专利
    • HEAT TRANSPORTING SYSTEM CONNECTING STEAM EXTRACTER AND DISTILLING APPARATUS OF ATOMIC INSTALLATION
    • JPS55127187A
    • 1980-10-01
    • JP3360879
    • 1979-03-22
    • ISHIKAWAJIMA HARIMA HEAVY IND
    • KAWANA SEIZOUSAWAZAKI TAKESHI
    • C02F1/16G21D7/04G21D9/00
    • PURPOSE:To make it possible to prevent the leakage of a harmful substance component to any direction by a mechanism wherein two or more of an intermediate heat exchanger is provided between the titled extracting portion and the water producing apparatus as well as the heat medium pressure flowing therebetween is raised to the maximum degree within the titled heat transporting system. CONSTITUTION:The steam s from a turbo-steam extractor 1 of an atomic power plant is flowed into the first intermediate heat exchanger 2b and returned to a condencer of a power plant while the heat is supplied to a heat medium h circulating within an arranged pipe 2c. The heat of the above described heat medium h is supplied to a relatively low pressure heat medium h circulating within an arranged pipe system 2e in the second intermediate heat exchanger 2d. This heat is supplied to sea water o in a brine heater 3a of a water producing apparatus 3 and the heat treasport from an extracting portion 1 to an apparatus 3. Therefor, if the heat exchanger 2b, 2d are normally operated, the leakage from an apparatus to a power plant side is completely prevented even if a heater 3a is damaged. Moreover, even if both heat exchangers are damaged, the radioactive substance which may be contained within an arranged pipe system 2a is not leaked because the medium pressure within an arranged pipe system 2c is high. At the same time, Cl within sea water is not leaked to a power plant side.
    • 49. 发明专利
    • Emergency power supply system
    • 紧急电源系统
    • JP2013104790A
    • 2013-05-30
    • JP2011249075
    • 2011-11-14
    • Toshiba Corp株式会社東芝
    • KITAMURA TAKUSAKAI NORIOTAKEUCHI YUTAKASAKURAI SHUNGOTAKIWAKI KENYA
    • G21D3/04G21D7/04H01L35/30
    • Y02E30/40
    • PROBLEM TO BE SOLVED: To enable a stable supply of emergency power when all power sources are lost.SOLUTION: An emergency power supply system includes: a chemical heat storage facility 11 that includes a reaction vessel 16 filled with a heat storage medium 28 and a storage container 17 connected to the reaction vessel via a communication pipe 18 and stores heat using a chemical reaction of the heat storage medium to radiate the heat; a first heat exchange loop 13 for performing heat exchange between the storage container and a nuclear reactor vessel primary system to heat the storage container; a thermoelectric conversion device 12 for generating electricity by a temperature difference between a high-temperature part 12A and a low-temperature part 12B; a second heat exchange loop 14 for performing heat exchange between the reaction vessel and a high-temperature part of the thermoelectric conversion device to heat the high-temperature part; and a final radiation cooling loop 15 for performing heat exchange between a low-temperature part of the thermoelectric conversion device and a final heat sink 25 to cool the low-temperature part. Further, a valve disposed in the first heat exchange loop 13 passively open-operates when power is lost to cause the storage container to be heated by a nuclear reactor vessel primary coolant to radiate the heat stored in the chemical heat storage facility 11 so that the thermoelectric conversion device 12 generates power using the heat.
    • 要解决的问题:为了在所有电源丢失时能够稳定地提供应急电源。 解决方案:应急电源系统包括:化学蓄热设备11,其包括填充有蓄热介质28的反应容器16和经由连通管18连接到反应容器的储存容器17,并且使用 蓄热介质的化学反应来散热; 第一热交换回路13,用于在存储容器和核反应堆容器主系统之间进行热交换以加热存储容器; 用于通过高温部分12A和低温部分12B之间的温度差发电的热电转换装置12; 用于在反应容器和热电转换装置的高温部分之间进行热交换以加热高温部分的第二热交换回路14; 以及用于在热电转换装置的低温部分和最终散热器25之间进行热交换以最终冷却低温部分的最终辐射冷却回路15。 此外,当功率消失时,设置在第一热交换回路13中的阀被动地打开,以使存储容器被核反应堆容器的一次冷却剂加热,以辐射存储在化学储热设备11中的热量, 热电转换装置12使用热量来发电。 版权所有(C)2013,JPO&INPIT
    • 50. 发明专利
    • NUCLEAR POWER PLANT
    • JP2001242287A
    • 2001-09-07
    • JP2000050990
    • 2000-02-28
    • TOSHIBA CORP
    • KONDO NARUHITOHARA AKIHIRO
    • G21D7/04H01L35/30H01L35/32
    • PROBLEM TO BE SOLVED: To provide a nuclear power plant wherein a thermoelectric converter for directly generating electricity is installed instead of a conventional steam generator installed in a reactor container. SOLUTION: This nuclear power plant is provided with a reactor pressure vessel for accommodating a reactor core and a primary coolant; a heat exchanger for transferring the heat of the primary coolant to a second coolant; and a connecting pipeline for connecting the reactor pressure vessel to the heat exchanger to allow the flow of the primary coolant. The thermoelectric converter comprising a thermoelectric generator having passages for the first coolant and second coolant to adjacently flow on the high temperature side and low temperature side of a thermoelectric element module, and generating power on the basis of the temperature difference is installed in the heat exchanger. Structural members for a large number of heat transfer pipes, a generator turbine and a generator heretofore required, and a building for enclosing them are thereby dispensed with to provide the nuclear power plant that can improve economic performance, simplify a system, facilitate maintenance and improve the operating rate and safety of the power plant.