JPS6275299A - Condenser exhaust-heat utilizer for nuclear power plant - Google Patents
Condenser exhaust-heat utilizer for nuclear power plantInfo
- Publication number
- JPS6275299A JPS6275299A JP60215937A JP21593785A JPS6275299A JP S6275299 A JPS6275299 A JP S6275299A JP 60215937 A JP60215937 A JP 60215937A JP 21593785 A JP21593785 A JP 21593785A JP S6275299 A JPS6275299 A JP S6275299A
- Authority
- JP
- Japan
- Prior art keywords
- heat
- water
- condenser
- nuclear power
- power plant
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Landscapes
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は原子力発電プラントの復水器排熱利用装置に係
り、特に、原子力発電プラントのタービン復水温から排
出される排熱の有効利用を図った原子力発電プラントの
１す水器排熱刊用装；Ｕに閏する。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a condenser exhaust heat utilization device for a nuclear power plant, and in particular, to an apparatus for effectively utilizing exhaust heat discharged from a turbine condensate temperature of a nuclear power plant. A nuclear power plant's water tank exhaust heat equipment;
以下、第３図を参照して従来の原子カブラン１−を説明
する。Hereinafter, the conventional atomic converter 1- will be explained with reference to FIG.
第３図は原子力発電プラントの概略格成を示しており、
原子炉圧力容器１内の炉心２の核反応熱により冷却材を
沸騰さ′ぜて（りられた蒸気は主蒸気管４を通って蒸気
タービン５に送気される。これにより、蒸気タービン５
は発電機６を回転さ「て発電１゛る。蒸気タービン５で
仕事をした蒸気は蒸気タービン５の下方に設置した復水
器７内に導入され、ここで循環水ポンプ８にＪ：り海水
冷ＮＨ＆束９に供給される海水により冷ＩＪＩ凝縮され
て復水となる。この復水は、低圧復水ポンプ１０により
復水配管１１を介してろ過般塔装置１２、高圧復水ポン
プ１３および給水加熱Ｚ１４に順次移送される。給水加
熱器１４には抽気配管１５と抽気ドレン配管１６が設置
ノられており、蒸気タービン５からの抽気然気により復
水を加温し、抽気ドレンは再び復水器７へ戻される。給
水加熱器１４で加温された復水は給水ポンプ３により給
水配管１７を通って再び原子炉圧力容７！Ａ１へ供給さ
れる。Figure 3 shows the schematic structure of a nuclear power plant.
The coolant is boiled by the nuclear reaction heat of the core 2 in the reactor pressure vessel 1, and the steam is sent to the steam turbine 5 through the main steam pipe 4.
generates electricity by rotating the generator 6. The steam that has done work in the steam turbine 5 is introduced into the condenser 7 installed below the steam turbine 5, where it is fed to the circulating water pump 8. The seawater supplied to the seawater-cooled NH & bundle 9 is condensed into condensate.This condensate is passed through a condensate pipe 11 by a low-pressure condensate pump 10 to a filtration unit 12 and a high-pressure condensate pump 13. The feed water heater 14 is equipped with a bleed air pipe 15 and a bleed drain pipe 16, and the condensate is heated by the bleed air from the steam turbine 5, and the bleed water is The condensate is returned to the condenser 7 again.The condensate heated by the feed water heater 14 is supplied to the reactor pressure vessel 7!A1 again through the water supply pipe 17 by the feed water pump 3.
しかしながら、このような従来の原子カブラン１へでは
、蒸気タービン５で仕事をした蒸気を復水器７にＪ３い
て海水により冷却凝縮して復水とするため、海水はこの
熱交換弁だけ温度が上昇して海洋に排出される。この復
水器７において排出される熱間は、例えば１１０万ＫＷ
ｅ級の沸騰水型原子力発電プラントの場合では約２．２
８ｘ１０６ＫＷに達しており、５吊の排熱となっている
。この袂熱のＶＪ′ｆｉとしては一般に、復水器７にお
ける海水の温度上背を７℃以下に抑えているために、例
えば復水器７の入［１海水温度を１５℃とすると、その
出口温度は約２２℃程度であり、大きな温度上昇が！！
ＩＪ持できない。このために、復水器７からの排熱の利
用方法が制約され、一部の発電所では海水温排水利用に
よる魚貝類の養殖を実施した例がある程度であった。However, in such a conventional atomic converter 1, the steam that has done work in the steam turbine 5 is sent to the condenser 7, where it is cooled and condensed by seawater to form condensate. It rises and is discharged into the ocean. The hot energy discharged in this condenser 7 is, for example, 1.1 million KW.
Approximately 2.2 in the case of an e-class boiling water nuclear power plant
It has reached 8x106KW, resulting in 5 units of waste heat. Generally speaking, the VJ'fi of this heat is to suppress the temperature of the seawater in the condenser 7 to 7 degrees Celsius or less. The outlet temperature is about 22℃, which is a big temperature rise! !
I can't have IJ. For this reason, the method of utilizing the exhaust heat from the condenser 7 is restricted, and some power plants have to some extent used seawater temperature wastewater to cultivate fish and shellfish.
本発明は上記事情に鑑みてなされたもので、その目的は
原子力発電プラントで復水器から放出されている排熱を
有効に利用することができる原子力発電プラントの復水
器排熱利用装置を提供することにある。The present invention has been made in view of the above circumstances, and its purpose is to provide a condenser exhaust heat utilization device for a nuclear power plant that can effectively utilize the exhaust heat released from the condenser in the nuclear power plant. It is about providing.
本発明は、原子力発電プラントの復水器より排熱を効率
よく回収し、この排熱を水冷式ヒートポンプの採熱源と
して利用し、温水または４ Ｊｕｌを供給する熱供給設
備を設けたことを特徴とする。The present invention is characterized by providing heat supply equipment that efficiently recovers waste heat from a condenser of a nuclear power plant, uses this waste heat as a heat collection source for a water-cooled heat pump, and supplies hot water or 4 Jul. shall be.
（発明の実施例〕
以下、第１図および第２図を参照して本発明の詳細な説
明する。なＪ３、第３図で示す部分と同一部分には同一
符号をイ］シてその説明は省略する。(Embodiments of the Invention) Hereinafter, the present invention will be described in detail with reference to FIG. 1 and FIG. is omitted.
第１図は本発明の一実施例の全体構成を示しており、復
水器７内に尚水冷ＩＪＩ管束９の一部を区切って淡水冷
却管束２１を設けている。この淡水冷却管束２１は淡水
循環ポンプ２２°を介装したループ状の淡水循環配Ｔ’
Ｊ ２３の管束よりなり、水冷式ピー１−ポンプ２８の
蒸発器２４の二次側を介装しており、復水器７内で蒸気
と熱交換して昇温した淡水を循環さける。そして、蒸気
タービン５で仕事をした蒸気の排熱の一部を淡水冷却管
束２１内。FIG. 1 shows the overall configuration of an embodiment of the present invention, in which a freshwater cooling tube bundle 21 is provided in a condenser 7 by separating a part of a water-cooled IJI tube bundle 9. This freshwater cooling pipe bundle 21 is a loop-shaped freshwater circulation pipe T' in which a freshwater circulation pump 22° is interposed.
It consists of a tube bundle of J23, and is interposed on the secondary side of the evaporator 24 of the water-cooled P1-pump 28, and circulates fresh water heated by heat exchange with steam in the condenser 7. Then, a part of the exhaust heat of the steam that has done work in the steam turbine 5 is transferred into the freshwater cooling pipe bundle 21 .
の淡水を介して回収し、圧縮機２５．膨張弁２６、蒸発
器２４おＪ：び冷媒配管２７からなる水冷式ヒートポン
プ２８の蒸発器２４の加熱源として、この排熱を利用で
きるように構成している。また、このようにして採熱し
た熱にＪ−り温水器３１を介して外部温水ループ３５の
渇水を加温し、温水ポンプ３２により渇水配管３３を通
って被加温設備の温水ヒータ３４へ温水を供給でるよう
に構成する。The fresh water is recovered through the compressor 25. The exhaust heat is configured to be used as a heating source for the evaporator 24 of the water-cooled heat pump 28, which includes an expansion valve 26, an evaporator 24, and a refrigerant pipe 27. In addition, the heat thus collected is used to heat the drought water in the external hot water loop 35 via the J-type water heater 31, and is sent to the hot water heater 34 of the equipment to be heated through the water shortage pipe 33 by the hot water pump 32. Configure to supply hot water.
第２図は本発明の他の実施例を示す。第１図の実施例と
主に異なるところは、水冷式ヒートポンプ２８で採熱し
た熱を温風器３６の加熱源として利用し送１！ｌ１ｌｉ
３７により温風を必要とづる被加温設備３８へ供給でき
るようにした点である。FIG. 2 shows another embodiment of the invention. The main difference from the embodiment shown in FIG. 1 is that the heat collected by the water-cooled heat pump 28 is used as a heating source for the hot air fan 36. l1li
37, it is possible to supply hot air to the heating equipment 38 that requires it.
以上の各実施例の作用を説明する。The operation of each of the above embodiments will be explained.
第１図の実施例では復水器７内に設置した淡水冷ＩＪ１
管束２１内の淡水の出口温度は復水器７内の運転圧力（
真空７２２８ａｔｌ（１）に応じて約３０℃程度とく蒙
る。この淡水は水冷式と−トボンブ２８の蒸発Ｚ２／Ｉ
を加熱しヒートポンプ運転によって４水器３１で外部温
水ループ３５に４０〜７０℃の温水を供給することがで
きる。In the embodiment shown in FIG.
The outlet temperature of the fresh water in the tube bundle 21 is determined by the operating pressure in the condenser 7 (
Depending on the vacuum 7228atl(1), the temperature is about 30°C. This fresh water is produced by water-cooling and evaporation Z2/I of Tobomb 28.
It is possible to supply hot water of 40 to 70° C. to the external hot water loop 35 with the four-water device 31 by heating the water and operating the heat pump.
また、第２図の実施例では、第１図で示す実施例とばば
同様の信用により被加温設備３８として、例えば温室や
住宅暖房に必要な２０〜３０℃の温圧を供給することが
できる。Furthermore, in the embodiment shown in FIG. 2, it is possible to supply a temperature and pressure of 20 to 30 degrees Celsius necessary for heating a greenhouse or a house, for example, as the heated equipment 38 based on the same reliability as in the embodiment shown in FIG. can.
〔発明の効果）
以上説明したように本発明は、従来原子力発電設備で復
水器から海水冷却水の温排水として海洋へ放出されてい
た排熱を、復水器内の冷ＩＪＩ材循環配管を介して回収
し、さらに、この排熱を水冷式ヒートポンプの採熱源と
外部の被加熱装置の熱利用に適した温度の温水または温
風を供給できる熱供給設備を設けたから、効率のよい排
熱利用を図ることができる。[Effects of the Invention] As explained above, the present invention utilizes waste heat, which was conventionally released from the condenser in nuclear power generation equipment to the ocean as heated waste water of seawater cooling water, to the cold IJI material circulation piping in the condenser. In addition, we have installed a heat supply facility that can supply hot water or hot air at a temperature suitable for the heat collection source of the water-cooled heat pump and the heat utilization of external heated devices, resulting in efficient exhaust heat. Heat can be utilized.
第１図および第２図は本発明に係る原子力発電プラント
の復水鼎排熱利用装置の各々の実施例を示ず系統図、第
３図は従来の沸騰水型原子力発電プラン］−を説明する
ための系統図である。
１・・・原子炉圧力容器、２・・・炉心、３・・・給水
ポンプ、４・・・主蒸気管、５・・・蒸気タービン、６
・・・発電様、７・・・復水器、８・・・循環水ポンプ
、９・・・海水冷Ｉｎ管束、１０・・・低圧復水ポンプ
、１１・・・復水配管、１２・・・ろ過説塩装置、１３
・・・高圧復水ポンプ、１４・・・給水加熱器、１５・
・・抽気配管、１６・・・油気ドレン配管、１７・・・
給水配管、２１・・・淡水冷７Ｊ］管束、２２・・・淡
水循環ポンプ、２３・・・淡水循環配管、２４・・・蒸
発器、２５・・・圧縮機、２６・・・膨張弁、２７・・
・冷媒配管、２８・・・水冷式ヒートポンプ、３１・・
・温水器、３２・・・温水ポンプ、３３・・・温水配管
、３４・・・温水ヒータ、３５・・・温水ループ、３６
・・・温風器、３７・・・送Ｊ！Ｉｉ１機、３８・・・
液加ｄｄ設備。Fig. 1 and Fig. 2 are system diagrams without showing respective embodiments of the condensate waste heat utilization device for a nuclear power plant according to the present invention, and Fig. 3 illustrates a conventional boiling water nuclear power generation plan. This is a system diagram for DESCRIPTION OF SYMBOLS 1... Reactor pressure vessel, 2... Reactor core, 3... Water supply pump, 4... Main steam pipe, 5... Steam turbine, 6
...Power generation, 7.Condenser, 8.Circulating water pump, 9.Seawater cooling In pipe bundle, 10.Low pressure condensate pump, 11.Condensate piping, 12. ...filtration theory salt device, 13
... High pressure condensate pump, 14... Feed water heater, 15.
...Air bleed pipe, 16...Oil drain pipe, 17...
Water supply piping, 21... Freshwater cold 7J] tube bundle, 22... Freshwater circulation pump, 23... Freshwater circulation piping, 24... Evaporator, 25... Compressor, 26... Expansion valve, 27...
・Refrigerant piping, 28...Water-cooled heat pump, 31...
・Water heater, 32... Hot water pump, 33... Hot water piping, 34... Hot water heater, 35... Hot water loop, 36
... air warmer, 37... send J! Ii 1 machine, 38...
Liquid addition dd equipment.
Claims (1)
発電させ、そのタービン発電機で仕事を終えた蒸気を冷
却凝縮させる海水冷却管束を復水器内に設けた原子力発
電プラントのものにおいて、水冷式ヒートポンプの蒸発
器内に熱交換可能に組み込まれ冷却材を循環させる冷却
材循環配管を上記復水器に設け、この水冷式ヒートポン
プからの熱を被加熱装置に供給する熱供給設備を設けた
ことを特徴とする原子力発電プラントの復水器排熱利用
装置。 ２、前記水冷式ヒートポンプは前記海水循環配管からの
熱によつて加熱される蒸発器、圧縮機、蓄熱部、冷媒配
管、膨張弁が順次接続されて前記蒸発器に接続される断
熱膨張サイクルである特許請求の範囲第１項記載の原子
力発電プラントの復水器排熱利用装置。[Scope of Claims] 1. A bundle of seawater cooling pipes is provided in the condenser to supply steam generated in the nuclear reactor to a turbine generator to generate electricity, and to cool and condense the steam that has finished its work in the turbine generator. In nuclear power plants, the condenser is equipped with coolant circulation piping that is built into the evaporator of the water-cooled heat pump for heat exchange and circulates the coolant, and the heat from the water-cooled heat pump is transferred to the heated equipment. A condenser exhaust heat utilization device for a nuclear power plant, characterized by being equipped with heat supply equipment. 2. The water-cooled heat pump is an adiabatic expansion cycle in which an evaporator heated by heat from the seawater circulation pipe, a compressor, a heat storage section, a refrigerant pipe, and an expansion valve are sequentially connected to the evaporator. A condenser exhaust heat utilization device for a nuclear power plant according to claim 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60215937A JPS6275299A (en) | 1985-09-27 | 1985-09-27 | Condenser exhaust-heat utilizer for nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60215937A JPS6275299A (en) | 1985-09-27 | 1985-09-27 | Condenser exhaust-heat utilizer for nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6275299A true JPS6275299A (en) | 1987-04-07 |
Family
ID=16680726
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60215937A Pending JPS6275299A (en) | 1985-09-27 | 1985-09-27 | Condenser exhaust-heat utilizer for nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6275299A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS643593A (en) * | 1987-06-26 | 1989-01-09 | Power Reactor & Nuclear Fuel | System for utilizing cooling heat of nuclear heated liquid |
| JP2011169539A (en) * | 2010-02-19 | 2011-09-01 | Mitsubishi Heavy Ind Ltd | Heat use system |
| JP2013087302A (en) * | 2011-10-14 | 2013-05-13 | M Hikari Energy Kaihatsu Kenkyusho:Kk | Method for utilizing seawater cooling water of nuclear power plant |
| JP2021516331A (en) * | 2017-12-29 | 2021-07-01 | ジョイント・ストック・カンパニー サイエンティフィック リサーチ アンド デザイン インスティテュート フォー エナジー テクノロジーズ アトムプロエクト | Condensate system to recover energy from nuclear power plants |
-
1985
- 1985-09-27 JP JP60215937A patent/JPS6275299A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS643593A (en) * | 1987-06-26 | 1989-01-09 | Power Reactor & Nuclear Fuel | System for utilizing cooling heat of nuclear heated liquid |
| JP2011169539A (en) * | 2010-02-19 | 2011-09-01 | Mitsubishi Heavy Ind Ltd | Heat use system |
| JP2013087302A (en) * | 2011-10-14 | 2013-05-13 | M Hikari Energy Kaihatsu Kenkyusho:Kk | Method for utilizing seawater cooling water of nuclear power plant |
| JP2021516331A (en) * | 2017-12-29 | 2021-07-01 | ジョイント・ストック・カンパニー サイエンティフィック リサーチ アンド デザイン インスティテュート フォー エナジー テクノロジーズ アトムプロエクト | Condensate system to recover energy from nuclear power plants |
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