JPH0158479B2 - - Google Patents
Info
- Publication number
- JPH0158479B2 JPH0158479B2 JP56109428A JP10942881A JPH0158479B2 JP H0158479 B2 JPH0158479 B2 JP H0158479B2 JP 56109428 A JP56109428 A JP 56109428A JP 10942881 A JP10942881 A JP 10942881A JP H0158479 B2 JPH0158479 B2 JP H0158479B2
- Authority
- JP
- Japan
- Prior art keywords
- boiling point
- point medium
- low boiling
- heat exchanger
- 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.)
- Expired
Links
- 238000009835 boiling Methods 0.000 claims description 37
- 230000001172 regenerating effect Effects 0.000 claims description 25
- 239000002826 coolant Substances 0.000 claims description 21
- 239000007788 liquid Substances 0.000 claims description 13
- 238000000746 purification Methods 0.000 claims description 13
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 11
- 238000001816 cooling Methods 0.000 claims description 9
- 238000010248 power generation Methods 0.000 claims description 7
- 230000005611 electricity Effects 0.000 claims description 2
- 239000000498 cooling water Substances 0.000 description 13
- 238000001914 filtration Methods 0.000 description 8
- 238000010586 diagram Methods 0.000 description 4
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 description 2
- 238000010795 Steam Flooding Methods 0.000 description 1
- 229910021529 ammonia Inorganic materials 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000004134 energy conservation Methods 0.000 description 1
- NBVXSUQYWXRMNV-UHFFFAOYSA-N fluoromethane Chemical compound FC NBVXSUQYWXRMNV-UHFFFAOYSA-N 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000010792 warming Methods 0.000 description 1
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)
Description
【発明の詳細な説明】
この発明は、沸騰水形原子力発電所の原子炉冷
却材浄化系の非再生熱交換器を熱源とする原子力
発電所の中温度利用発電設備に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to medium-temperature power generation equipment for a nuclear power plant that uses a non-regenerative heat exchanger of a reactor coolant purification system of a boiling water nuclear power plant as a heat source.
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つて浄化
されてから供給するようになつているが、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。 In boiling water nuclear power plants, reactor feed water is supplied after being purified from the turbine main condenser through a condensate demineralizer, but in order to maintain high core purity at all times, There is a reactor coolant purification system that continuously removes and purifies a portion of the reactor coolant from the reactor recirculation system.
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、ろ過脱塩器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℃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 reason why the extracted reactor coolant is passed twice from the regenerative heat exchanger 4 to the non-regenerative heat exchanger 5 is that the temperature of the reactor coolant processed by the filtration demineralizer 6 is high enough to function properly. Because it does not demonstrate
This is because it is necessary to cool the temperature to 60° C. or lower, which is the operating temperature of the filtration demineralizer 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によつて浄化された原子炉冷却材によ
つて冷却が行われ、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よりの冷却水によつて冷却を行つてい
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 transferred to the reactor pressure vessel 1. The non-regenerative heat exchanger 5 is used to warm the reactor coolant that is returned, but the non-regenerative heat exchanger 5 is cooled by cooling water from the reactor auxiliary cooling water system 8, and after cooling, it is directly transported to the ocean or river. Since the heat exchangers are disposed of in other places, there is a problem in terms of energy conservation, and there has been a demand for energy recovery measures for these non-regenerative heat exchangers.
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つた抵沸点媒
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エネルギーにして
回収する原子力発電所の中温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 steam 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 medium-temperature power generation equipment for nuclear power plants that connects the two to generate power and recover the thermal energy that was previously discarded as electrical energy.
この発明による原子力発電所の中温度利用発電
設備の一実施例を第2図に示す系統図によつて説
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、ろ過脱塩器1
3は原子炉冷却材浄化系14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11
及び非再生熱交換器12を通してろ過脱塩器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1
6に戻している。 An embodiment of the medium-temperature power generation equipment for a nuclear power plant according to the present invention will be explained with reference to the system diagram shown in FIG. In FIG. 2, a circulation pump 10, a regenerative heat exchanger 11, a non-regenerative heat exchanger 12, a filtration demineralizer 1
3 constitutes a reactor coolant purification system 14, in which a part of the reactor coolant is taken out by a circulation pump 10 from a reactor recirculation system piping 15 connected to a reactor pressure vessel (not shown in the drawing). Regenerative heat exchanger 11
and a filtration demineralizer 13 through a non-regenerative heat exchanger 12
After cooling to the proper operating temperature of the filtration demineralizer 13
After passing through the regenerative heat exchanger 11 and warming it, the water supply pipe 1 is connected from the reactor condensate system (not shown in the drawing) to the reactor pressure vessel (not shown in the drawing).
It's back to 6.
循環ポンプ10によつ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によつ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℃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を駆動し、
その抵沸点媒体タービン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2
0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
によつて昇圧され給液配管26を介して再び原子
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18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が配設されている。また、前記給液配
管26には液状の低沸点媒体を貯蔵するための低
沸点媒体貯槽25が接続配管27を介して接続さ
れている。 The reactor coolant sent by the circulation pump 10 is purified by the filtration demineralizer 13 in the regenerative heat exchanger 11, and the reactor coolant is returned to the water supply pipe 16, which removes heat. After being cooled to a temperature of For cooling at 12, a low boiling point medium such as fluorocarbon or ammonia is used. 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. death,
A generator 19 connected to the low boiling point medium turbine 18 is rotated to generate electricity. The low boiling point medium vapor that has finished its work in the low boiling point medium turbine 18 is sent to the condenser 2.
0, is cooled by the cooling water from the reactor auxiliary cooling water system 21, becomes liquid, and is supplied to the liquid supply pump 22.
The pressure is increased by the liquid supply pipe 26, and the liquid is again sent to the cooling heat exchanger tube 17 of the non-regenerative heat exchanger 12 of the reactor coolant purification system. Furthermore, when repairing the low boiling point medium turbine 18 or the generator 19,
In order to direct the low-boiling medium vapor directly to the condenser 20,
A turbine bypass valve 23 and a bypass pipe 24 connecting the turbine bypass valve 23 are provided. Further, a low boiling point medium storage tank 25 for storing a liquid low boiling point medium is connected to the liquid supply pipe 26 via a connecting pipe 27.
この発明による原子力発電所の中温度利用発電
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つてタービン発電機
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
発電所の中温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 intermediate temperature power generation equipment for a nuclear power plant according to the present invention has the following features, as described in detail in the embodiments above:
In the reactor coolant purification system of a boiling water nuclear power plant, a low boiling point medium such as Freon is used to recover the heat to cool the non-regenerative heat exchanger;
The generated low-boiling medium steam drives a turbine generator and converts it into electrical energy, which is used for internal power, etc., which saves a large amount of thermal energy that was previously disposed of through the reactor auxiliary cooling water system. It has the advantage that parts can be recovered. In addition, the cooling water of the reactor auxiliary cooling water system is also used in the medium-temperature power generation equipment of the nuclear power plant according to the present invention to liquefy the low-boiling 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.
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
所の中温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、1
9……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……低沸点媒体貯
槽、26……給液配管、27……接続配管。
Figure 1 is a system diagram of a conventional reactor coolant purification system.
FIG. 2 is a system diagram of a medium-temperature power generation facility in a nuclear power plant in an embodiment of the present invention. 12, 5...Non-regenerative heat exchanger, 14...Reactor coolant purification system, 18...Low boiling point medium turbine, 1
9... Generator, 20... Condenser, 21, 8... Reactor auxiliary cooling water system, 22... Liquid supply pump, 23...
...Turbine bypass valve, 25...Low boiling point medium storage tank, 26...Liquid supply piping, 27...Connection piping.
Claims (1)
において、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、その抵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、液体となつた低沸点媒体を前
記非再生熱交換器に給液配管を介して送り込む給
液ポンプと、前記給液配管に接続配管を介して接
続され液状の低沸点媒体を貯蔵する低沸点媒体貯
槽と、低沸点媒体蒸気を前記低沸点媒体タービン
をバイパスしタービンバイパス弁を介して直接前
記凝縮器に導くバイパス管路とを備え、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わせるよ
うにした原子力発電所の中温度利用発電設備。1. In the reactor coolant purification system of a boiling water nuclear power plant, a low boiling point medium is used to cool the non-regenerative heat exchanger, and the system is driven by the low boiling point medium vapor generated in the non-regenerative heat exchanger. a low boiling point medium turbine, a generator rotated by the low boiling point medium turbine, a condenser that cools and liquefies the low boiling point medium vapor that has finished work in the low boiling point medium turbine, and a low boiling point medium vapor that has become a liquid. a liquid supply pump that sends a medium to the non-regenerative heat exchanger via a liquid supply pipe; a low boiling point medium storage tank that is connected to the liquid supply pipe via a connecting pipe and stores a liquid low boiling point medium; and a low boiling point medium. a bypass pipe line that bypasses the low-boiling point medium turbine and directly leads the steam to the condenser via the turbine bypass valve, the low-boiling point medium being used for cooling the non-regenerative heat exchanger of the reactor coolant purification system. This is a medium-temperature power generation facility at a nuclear power plant that uses water 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 JPS5811896A (en) | 1983-01-22 |
| JPH0158479B2 true 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 |
|---|---|---|---|---|
| JPH03119321U (en) * | 1990-03-16 | 1991-12-09 |
Families Citing this family (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 |
-
1981
- 1981-07-15 JP JP56109428A patent/JPS5811896A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03119321U (en) * | 1990-03-16 | 1991-12-09 |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5811896A (en) | 1983-01-22 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| WO2023178872A1 (en) | System and method for realizing transformation of thermal power generating unit on basis of combined high- and low-parameter fused salts | |
| JPS57191407A (en) | Rankine cycle system | |
| JPS61171808A (en) | Dual rankine cycle power plant | |
| JPH0158479B2 (en) | ||
| JP2002122006A (en) | Power generation equipment utilizing low-temperature exhaust heat | |
| JPS598641B2 (en) | heat cycle equipment | |
| JP3147322B2 (en) | Absorption chiller / heater | |
| JPS59180012A (en) | Combined cycle turbine power plant utilizing liquefied natural gas and low-boiling point medium | |
| JPS58138213A (en) | Power generation device | |
| JPS6086494A (en) | Nuclear power plant waste heat concentrating recovering utilizing device | |
| JPS6274499A (en) | Removal of scale in hot spring water | |
| JPS58202313A (en) | Thermal power plant using low temperature liquefied gas as fuel | |
| JPH04124411A (en) | Steam turbine combine generator equipment | |
| JPH04292757A (en) | Cogeneration plant system | |
| JPS6042842B2 (en) | thermal power generation device | |
| JPS5935560Y2 (en) | Blast furnace furnace body waste heat recovery device | |
| JPH08200017A (en) | Rankine cycle of thermal power plant | |
| JPH06108804A (en) | Power generating system | |
| JP3068288B2 (en) | Auxiliary cooling water system for nuclear power plants | |
| JPH04124594A (en) | Heat and electricity parallel supplying device | |
| JPS5827211Y2 (en) | High pressure feed water heater cooling system | |
| JPS6010594B2 (en) | nuclear power plant | |
| JP2806493B2 (en) | Combined cooling system | |
| JPS5791304A (en) | Electric power generator | |
| JPH0478883B2 (en) |