JPS5811896A - Medium temperature using power facility of atomic power plant - Google Patents
Medium temperature using power facility of atomic power plantInfo
- Publication number
- JPS5811896A JPS5811896A JP56109428A JP10942881A JPS5811896A JP S5811896 A JPS5811896 A JP S5811896A JP 56109428 A JP56109428 A JP 56109428A JP 10942881 A JP10942881 A JP 10942881A JP S5811896 A JPS5811896 A JP S5811896A
- Authority
- JP
- Japan
- Prior art keywords
- low
- boiling point
- medium
- heat exchanger
- point medium
- 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.)
- Granted
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
-
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engine Equipment That Uses Special Cycles (AREA)
- Physical Or Chemical Processes And Apparatus (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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
この発明は、沸騰水形原子力発電ル1の原子炉冷却材浄
化系の非再生熱交換器を熱源とする原子力発電所の中湿
度利用発電設備に関する0沸騰水形原子力発電所におい
ては、原子炉給水はタービン主復水器から復水脱塩器を
通って浄化されてから供給されるようになっているが、
炉心純度を常に高く保つために、別に原子炉冷却材の一
部を原子炉再循環系から連続的に取り出して浄化する原
子炉冷却材浄化系がある。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a zero boiling water nuclear power generation facility that uses a medium humidity utilization power generation facility in a nuclear power plant that uses a non-regenerative heat exchanger of a reactor coolant purification system of a boiling water nuclear power generation unit 1 as a heat source. At power plants, reactor feed water is purified from the turbine main condenser through a condensate demineralizer before being supplied.
In order to maintain high core purity at all times, there is a separate reactor coolant purification system that continuously removes a portion of the reactor coolant from the reactor recirculation system and purifies it.
第1図は従来の原子炉冷却材浄化系の系統図で、原子炉
圧力容器1に接続された原子炉再循環系配管2から原子
炉冷却材の一部を原子炉冷却材浄化系循環ポンプ3によ
り取り出し、順次再生熱交換器4と非再生熱交換器5を
通して冷却した後、ろ過脱塩器6に導いて浄化し、つい
で再び再生熱交換器4を通して温めた後、復水系(図面
では省略)からの給水配管7を経て原子炉圧力容器1に
戻している。取り出した原子炉冷却材を再生熱交換器4
から非再生熱交換器5へと二重に通しているのは、ろ過
説塩器6が処理する原子炉冷却材の温度が高いと十分な
機能を発揮しないので、その温度をろ過脱塩器6の作動
温度である60°C以下にまで冷却する必要があるため
である。Figure 1 is a system diagram of a conventional reactor coolant purification system, in which a part of the reactor coolant is transferred from the reactor recirculation system piping 2 connected to the reactor pressure vessel 1 to the reactor coolant purification system circulation pump. 3, and after being cooled sequentially through a regenerative heat exchanger 4 and a non-regenerative heat exchanger 5, it is introduced into a filtration demineralizer 6 for purification, and then heated again through a regenerative heat exchanger 4. The water is returned to the reactor pressure vessel 1 via a water supply pipe 7 from (omitted). The extracted reactor coolant is regenerated into heat exchanger 4.
The reason why the reactor coolant processed by the filtration demineralizer 6 does not function sufficiently is that it passes through the non-regenerative heat exchanger 5 twice. This is because it is necessary to cool down to 60° C. or lower, which is the operating temperature of No. 6.
上記2組の熱交換器の内、再生熱交換器4はろ過脱塩器
6によって浄化された原子炉冷却材によって冷却が行わ
れ、その時の熱エネルギーは原子炉圧力容器1に戻す原
子炉冷却材を温めるのに利用しているが、非再生熱交換
器5は原子炉補機冷却水系8よりの冷却水によって冷却
を行っていて、冷却後はそのまま海洋や川などへ廃棄さ
れているので、省エネルギー上問題があり、この非再生
熱交換器に対するエネルギー回収対策が要望されていた
。Of the above two sets of heat exchangers, the regenerative heat exchanger 4 is cooled by the reactor coolant purified by the filtration demineralizer 6, and the thermal energy at that time is returned to the reactor pressure vessel 1 for reactor cooling. However, the non-regenerative heat exchanger 5 is cooled by cooling water from the reactor auxiliary cooling water system 8, and after cooling is disposed of directly into the ocean or river. However, there is a problem in terms of energy conservation, and there has been a demand for energy recovery measures for this non-regenerative heat exchanger.
この発明は、上記の事情に鑑みてなされたもので、沸騰
水形原子力発電所の原子炉冷却材浄化系に使用している
非再生熱交換器において、冷却するのに原子炉補機冷却
水系よりの冷却水の代りにフロンのような低沸点媒体を
使用し、冷却に際し相手側の熱により蒸発して蒸気とな
った低沸点媒体蒸気により低沸点媒体タービンを運転し
、そのタービンに発電機を連結して発電を行い、従来廃
棄していた熱エネルギーを電気工ネルキーにして回収す
る原子力発電所の中湿度利用発電設備を提供することを
目的とする。This invention has been made in view of the above circumstances, and in a non-regenerative heat exchanger used in a reactor coolant purification system of a boiling water nuclear power plant, the reactor auxiliary cooling water system is used for cooling. A low-boiling point medium such as chlorofluorocarbons is used instead of cooling water, and the low-boiling point medium vapor is evaporated into steam by the heat of the other side during cooling, and the low-boiling point medium steam is used to operate the low-boiling point medium turbine, and the turbine is connected to a generator. The purpose of the present invention is to provide power generation equipment that utilizes medium humidity in a nuclear power plant, which connects the two to generate power, and recovers the thermal energy that was previously discarded as electrician energy.
この発明による原子力発電所の中湿度利用発電設備の一
実施例を第2図ζこ示す系統図によって説明する。第2
図において循環ポンプ10.再生熱交換器11.非再生
熱交換器12.ろ過説塩器13は原子炉冷却材浄化系1
4を構成していて、原子炉圧力容器(図面では省略)に
接続された原子炉再循環系配管15から原子炉冷却材の
一部を循環ポンプ10により取り出し、再生熱交換器1
1及び非再生熱交換器12を通しでろ過脱塩器13の適
正作動温度まで冷却した後、ろ過脱塩器13に導いて浄
化し、ついで再生熱交換器11を通して温めた後、原子
炉復水系(図面では省略)から原子炉圧力容器(図面で
は省略)への給水配管16に戻している。An embodiment of the medium humidity power generation equipment for a nuclear power plant according to the present invention will be described with reference to a system diagram shown in FIG. Second
In the figure, circulation pump 10. Regenerative heat exchanger 11. Non-regenerative heat exchanger12. The filtration system 13 is the reactor coolant purification system 1
A part of the reactor coolant is taken out by the circulation pump 10 from the reactor recirculation system piping 15 which constitutes the reactor pressure vessel (not shown in the drawing) and is connected to the reactor pressure vessel (not shown in the drawing).
1 and a non-regenerative heat exchanger 12 to the appropriate operating temperature of the filtration demineralizer 13, then led to the filtration demineralizer 13 for purification, then warmed through the regenerative heat exchanger 11, and then cooled to the proper operating temperature of the filtration demineralizer 13. The water is returned to the water supply pipe 16 from the water system (not shown in the drawing) to the reactor pressure vessel (not shown in the drawing).
循環ポンプ10によって送り込まれる原子炉冷却材は、
再生熱交換器11において、ろ過脱塩器13によって浄
化されて給水配管16に戻される原子炉冷却材に熱を奪
われて、ある温度まで冷却された後非再生熱交換器12
に導かれ、更にろ過脱塩器13の適正作動温度(60°
C以下)にまで冷却されているが、この発明においては
、この非再生熱交換器12における冷却には、例えばフ
ロンあるいはアンモニアのような低沸点媒体を使用して
いる。低沸点媒体は非再生熱交換器12の冷却用伝熱管
17を通過中に自らは熱せられて蒸発し、発生した低沸
点媒体蒸気は低沸点媒体タービン18に導かれて、この
タービン18を駆動シ、その低沸点媒体タービン18に
連結された発電機19を回転させて発電させる。低沸点
媒体タービン18で仕事を終えた低沸点媒体蒸気は凝縮
器20に導かれ、原子炉補機冷却水系21よりの冷却水
により冷却されて液状となり、給液ポンプ22によって
再び原子炉冷却材浄化系非再生熱交換器12の冷却用伝
熱管17に送り込まれる。更に、低沸点媒体タービン1
8または発電機19を補修するなどの場合、低沸点媒体
蒸気を直接凝縮(5)
器20に導くために、タービンバイパス弁23とそれを
接続するバイパス管路24とを設け、また、液状の低沸
点媒体を貯蔵するための低沸点媒体貯槽25を付属させ
ている。The reactor coolant sent by the circulation pump 10 is
In the regenerative heat exchanger 11 , heat is taken away by the reactor coolant that is purified by the filtration demineralizer 13 and returned to the water supply pipe 16 and cooled to a certain temperature, and then transferred to the non-regenerative heat exchanger 12
furthermore, the proper operating temperature of the filtration demineralizer 13 (60
In the present invention, a low boiling point medium such as fluorocarbon or ammonia is used for cooling in the non-regenerative heat exchanger 12. The low boiling point medium is heated and evaporated while passing through the cooling heat transfer tube 17 of the non-regenerative heat exchanger 12, and the generated low boiling point medium vapor is led to the low boiling point medium turbine 18 and drives this turbine 18. Then, the generator 19 connected to the low boiling point medium turbine 18 is rotated to generate electricity. The low-boiling point medium vapor that has completed its work in the low-boiling point medium turbine 18 is led to the condenser 20, where it is cooled by cooling water from the reactor auxiliary cooling water system 21 and becomes liquid, and is then returned to the reactor coolant by the feed pump 22. It is sent to the cooling heat exchanger tube 17 of the purification system non-regenerative heat exchanger 12. Furthermore, the low boiling point medium turbine 1
8 or the generator 19, a turbine bypass valve 23 and a bypass pipe 24 connecting it are provided in order to directly guide the low boiling point medium vapor to the condenser (5) 20. A low boiling point medium storage tank 25 is attached for storing a low boiling point medium.
この発明による原子力発電所の中湿度利用発電設備は、
実施例について前記に詳述したように、沸騰水形原子力
発電所の原子炉冷却材浄化系において、非再生熱交換器
を冷却するために、フロンのような低沸点媒体を使用し
てその熱を回収し、発生した低沸点媒体蒸気によってタ
ービン発電機を駆動して電気エネルギーに変換し、所内
動力などに利用するので、従来のように原子炉補機冷却
水系を経て廃棄していた熱エネルギーの大部分を回収す
ることができる利点がある。また、原子炉補機冷却水系
の冷却水は、この発明による原子力発電所の中湿度利用
発電設備においても低沸点媒体蒸気を液化さすために使
用しているが、原子炉冷却材浄化系の非再生熱交換器の
冷却に使用する量に比べれば僅かの量で済むので、原子
炉補機冷却水系に対する負担が軽減される効果がある。The medium-humidity power generation equipment for a nuclear power plant according to this invention is as follows:
As detailed above for example embodiments, in a reactor coolant purification system of a boiling water nuclear power plant, a low boiling point medium, such as chlorofluorocarbons, is used to cool a non-regenerative heat exchanger. The generated low-boiling medium steam is used to drive a turbine generator and convert it into electrical energy, which is used for in-house power, etc., so thermal energy that was previously disposed of through the reactor auxiliary cooling water system is used. It has the advantage of being able to recover most of the In addition, the cooling water of the reactor auxiliary cooling water system is also used in the medium humidity power generation equipment of the nuclear power plant according to the present invention to liquefy the low boiling point medium vapor, but the cooling water of the reactor auxiliary cooling water system is Since the amount required is small compared to the amount used for cooling the regenerative heat exchanger, it has the effect of reducing the burden on the reactor auxiliary equipment cooling water system.
(6)(6)
第1図は従来の原子炉冷却材浄化系の系統図、第2図は
この発明の一実施例における原子力発電所の中湿度利用
発電設備の系統図である。
12.5・・・非再生熱交換器、14・・・原子炉冷却
材浄化系、18・・・低沸点媒体タービン、19・・・
発電機、20・・・凝縮器、21,8・・・原子炉補機
冷却水系、22・・・給液ポンプ、23・・・タービン
バイパス弁、25・・・貯槽。
(7317) 代理人 弁理士 則近憲佑(ほか1名
)
(7)
第1図FIG. 1 is a system diagram of a conventional nuclear reactor coolant purification system, and FIG. 2 is a system diagram of a medium-humidity power generation facility in a nuclear power plant according to an embodiment of the present invention. 12.5...Non-regenerative heat exchanger, 14...Reactor coolant purification system, 18...Low boiling point medium turbine, 19...
Generator, 20... Condenser, 21, 8... Reactor auxiliary equipment cooling water system, 22... Liquid supply pump, 23... Turbine bypass valve, 25... Storage tank. (7317) Agent Patent attorney Kensuke Norichika (and 1 other person) (7) Figure 1
Claims (1)
非再生熱交換器の冷却に低沸点媒体を使用するようにし
、その非再生熱交換器において発生された低沸点媒体蒸
気により駆動される低沸点媒体タービンと、その低沸点
媒体タービンにより回転される発電機と、前記低沸点媒
体タービンにおいて仕事を終えた低沸点媒体蒸気を冷却
して液化さす凝縮器と、液体となった低沸点媒体を前記
非再生熱交換器に送り込む給液ポンプき、液状の低沸点
媒体を貯蔵する貯槽と、低沸点媒体蒸気を前記低沸点媒
体タービンをバイパスして直接前記凝縮器に導くタービ
ンバイパス弁とを備え、前記原子炉冷却材浄化系の非再
生熱交換器の冷却に使用する低沸点媒体を作動媒体とし
て発電を行れせるようζこした原子力発電所の中湿度利
用発電設備。In the reactor coolant purification system of boiling water nuclear power plants,
A low boiling point medium is used for cooling the non-regenerative heat exchanger, and a low boiling point medium turbine is driven by the low boiling point medium steam generated in the non-regenerative heat exchanger, and the low boiling point medium turbine is rotated by the low boiling point medium turbine. a generator, a condenser that cools and liquefies the low-boiling medium vapor that has finished work in the low-boiling medium turbine, and a feed pump that feeds the liquid low-boiling medium to the non-regenerative heat exchanger; a non-regenerative heat exchanger of the reactor coolant purification system, comprising: a storage tank for storing a low-boiling point medium; and a turbine bypass valve that bypasses the low-boiling point medium turbine and directly leads the low-boiling point medium vapor to the condenser; A power generation facility using medium humidity at a nuclear power plant that uses a low boiling point medium used for cooling as a working medium to generate electricity.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56109428A JPS5811896A (en) | 1981-07-15 | 1981-07-15 | Medium temperature using power facility of atomic power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56109428A JPS5811896A (en) | 1981-07-15 | 1981-07-15 | Medium temperature using power facility of atomic power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5811896A true JPS5811896A (en) | 1983-01-22 |
| JPH0158479B2 JPH0158479B2 (en) | 1989-12-12 |
Family
ID=14509990
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56109428A Granted JPS5811896A (en) | 1981-07-15 | 1981-07-15 | Medium temperature using power facility of atomic power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5811896A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62148894A (en) * | 1985-12-24 | 1987-07-02 | 動力炉・核燃料開発事業団 | Heavy-water heat utilization system of nuclear reactor |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03119321U (en) * | 1990-03-16 | 1991-12-09 |
-
1981
- 1981-07-15 JP JP56109428A patent/JPS5811896A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62148894A (en) * | 1985-12-24 | 1987-07-02 | 動力炉・核燃料開発事業団 | Heavy-water heat utilization system of nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0158479B2 (en) | 1989-12-12 |
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