JPH0252240B2 - - Google Patents
Info
- Publication number
- JPH0252240B2 JPH0252240B2 JP56012691A JP1269181A JPH0252240B2 JP H0252240 B2 JPH0252240 B2 JP H0252240B2 JP 56012691 A JP56012691 A JP 56012691A JP 1269181 A JP1269181 A JP 1269181A JP H0252240 B2 JPH0252240 B2 JP H0252240B2
- Authority
- JP
- Japan
- Prior art keywords
- hot water
- equipment
- heat exchanger
- reactor
- coolant
- 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 - Lifetime
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 58
- 239000002826 coolant Substances 0.000 claims description 33
- 239000000498 cooling water Substances 0.000 claims description 29
- 230000001172 regenerating effect Effects 0.000 claims description 27
- 238000000746 purification Methods 0.000 claims description 25
- 238000010248 power generation Methods 0.000 claims description 7
- 238000010438 heat treatment Methods 0.000 claims description 6
- 239000000295 fuel oil Substances 0.000 description 8
- 238000010586 diagram Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- 238000001816 cooling Methods 0.000 description 3
- 239000012535 impurity Substances 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 238000004378 air conditioning Methods 0.000 description 2
- 238000010612 desalination reaction Methods 0.000 description 2
- 230000001105 regulatory effect Effects 0.000 description 2
- 238000009423 ventilation Methods 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000002918 waste heat Substances 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
Description
【発明の詳細な説明】
本発明は、原子炉冷却材浄化系に生じる排熱を
有効に利用するようにした原子力発電設備に関す
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to nuclear power generation equipment that effectively utilizes exhaust heat generated in a nuclear reactor coolant purification system.
原子炉には第１図に示されるように原子炉圧力
容器ａ内の冷却材を浄化するための原子炉冷却材
浄化系ｂが設けられる。この浄化系ｂは、ポンプ
ｃ、再生熱交換器ｄ、非再生熱交換器ｅ、過脱
塩器等の浄化装置ｆなどから構成される。そして
圧力容器ａから取り出された冷却材は、再生熱交
換器ｄを通り、非再生熱交換器ｅにて所定の温度
に下げられてから、浄化装置ｆに送り込まれるよ
うになつている。そして浄化後の冷却材は再び再
生熱交換器ｄを通過することによつて、昇温して
圧力容器ａに環流されるものである。上記非再生
熱交換器ｅの冷却水配管ｇは、温度制御器ｂによ
つて流量が調整される温度調整弁ｉを介して冷却
水を循環させるようになつており、熱交換されて
高温となつた冷却水は冷却水戻り管ｊを通じて発
電所外に放出させている。 As shown in FIG. 1, the nuclear reactor is provided with a reactor coolant purification system b for purifying the coolant in the reactor pressure vessel a. This purification system b is composed of a pump c, a regenerative heat exchanger d, a non-regenerative heat exchanger e, a purification device f such as a super desalination device, and the like. The coolant taken out from the pressure vessel a passes through a regenerative heat exchanger d, is lowered to a predetermined temperature by a non-regenerative heat exchanger e, and is then sent to a purification device f. The coolant after purification is then passed through the regenerative heat exchanger d again to raise its temperature and then circulated into the pressure vessel a. The cooling water piping g of the non-regenerative heat exchanger e is designed to circulate cooling water through a temperature adjustment valve i whose flow rate is adjusted by a temperature controller b, and the cooling water is exchanged with high temperature. The cooled cooling water is discharged outside the power plant through the cooling water return pipe j.
ところで発電所内では換気空調系の暖房用とし
て、あるいは他の設備機器の加熱用としてボイラ
等で発生させた蒸気を用いており、この蒸気発生
用の熱源として一般に重油を使用しているが、大
規模なこの種発電所では多大な量の重油を必要と
している。 By the way, in power plants, steam generated by boilers, etc. is used for heating the ventilation air conditioning system or for heating other equipment, and heavy oil is generally used as the heat source for generating this steam. This type of power plant requires a large amount of heavy oil.
本発明は上記の事情のもとに開発されたもの
で、その目的は、原子炉本来の熱循環系の機能を
何ら損うことなく、原子炉冷却材浄化系で得られ
る排熱を利用して被加熱対象設備・機器を加熱し
て省エネルギー化を図ることができるとともに、
被加熱対象設備・機器が放射化されるおそれを確
実に防止できるようにした原子力発電設備を提供
することにある。 The present invention was developed under the above circumstances, and its purpose is to utilize the exhaust heat obtained from the reactor coolant purification system without impairing the function of the nuclear reactor's original thermal circulation system. It is possible to save energy by heating the equipment and equipment to be heated, and
It is an object of the present invention to provide nuclear power generation equipment that can reliably prevent the risk of radiation of equipment and equipment to be heated.
以下、本発明の第１実施例を第２図を参照して
説明する。図中１は原子炉圧力容器であつて、こ
の内部には図示しない炉心が収容されている。そ
して圧力容器１内で得られた冷却材の蒸気は、図
示しない主蒸気管から取り出されて発電タービン
を回して発電をなすようになつている。また、２
は原子炉冷却材浄化系を示し、この浄化系２は、
冷却材移送ポンプ３、再生熱交換器４、非再生熱
交換器５、過脱塩器等の浄化装置６などから構
成されている。上記非再生熱交換器５は、冷却水
配管７を介して冷却水を取り入れるものである。
この冷却水配管７の冷却水戻り管７ａには、温度
制御器８によつて流量調節される温度調整弁９が
設けられているとともに、この温度調整弁９の下
流側において開閉弁１０が設けられている。 A first embodiment of the present invention will be described below with reference to FIG. In the figure, reference numeral 1 denotes a reactor pressure vessel, in which a reactor core (not shown) is housed. The coolant steam obtained within the pressure vessel 1 is taken out from a main steam pipe (not shown) to rotate a power generation turbine and generate power. Also, 2
indicates the reactor coolant purification system, and this purification system 2 is
It is comprised of a coolant transfer pump 3, a regenerative heat exchanger 4, a non-regenerative heat exchanger 5, and a purification device 6 such as a super desalination device. The non-regenerative heat exchanger 5 takes in cooling water via a cooling water pipe 7.
The cooling water return pipe 7a of the cooling water pipe 7 is provided with a temperature regulating valve 9 whose flow rate is adjusted by a temperature controller 8, and an on-off valve 10 is provided downstream of the temperature regulating valve 9. It is being
また、上記冷却水戻り管７ａには、この管内を
流れる１次温水を熱源とする温水供給系１１が設
けられている。この温水供給系１１は、上記開閉
弁１０をバイパスして冷却水戻り管７ａに接続し
た２次熱交換器１２と、２次温水循環用ポンプ１
３と、被加熱対象設備・機器１４と、これらを互
いに連通接続した閉ループの温水配管１５とから
形成されている。 Further, the cooling water return pipe 7a is provided with a hot water supply system 11 whose heat source is primary hot water flowing through the pipe. This hot water supply system 11 includes a secondary heat exchanger 12 connected to a cooling water return pipe 7a bypassing the on-off valve 10, and a secondary hot water circulation pump 1.
3, equipment/equipment 14 to be heated, and a closed loop hot water piping 15 connecting these to each other.
次に上記第１実施例の作用について説明する。
原子炉圧力容器１から取り出された冷却材は、ポ
ンプ３によつて再生熱交換器４および非再生熱交
換器５に送り込まれ、この非再生熱交換器５にて
冷却水配管７に流れる冷却水と熱交換されて、所
定の温度まで冷却材の温度が下げられる。そし
て、浄化装置６に送られて浄化された後、再び再
生熱交換器４を通過し加熱されて、原子炉圧力容
器１内に環流される。 Next, the operation of the first embodiment will be explained.
The coolant taken out from the reactor pressure vessel 1 is sent to the regenerative heat exchanger 4 and the non-regenerative heat exchanger 5 by the pump 3, and in the non-regenerative heat exchanger 5, the coolant flows into the cooling water pipe 7. The temperature of the coolant is lowered to a predetermined temperature by exchanging heat with the water. After being sent to the purification device 6 and purified, it passes through the regenerative heat exchanger 4 again, is heated, and is circulated into the reactor pressure vessel 1.
一方、非再生熱交換器５を第１次熱源として熱
交換された冷却水配管７内の冷却水は、高温の戻
り水（１次温水）となつて冷却水戻り管７ａ内を
流れる。そして、被加熱対象設備・機器１４を加
熱する必要がない場合には、開閉弁１０は全開状
態に保持されて、１次温水は温水供給系１１を流
れることなく冷却水戻り管７ａを通過する。ま
た、被加熱対象設備・機器１４を加熱する場合、
開閉弁１０は全閉状態又は中間開度状態に保持さ
れるとともに、温水供給系１１の２次温水循環用
ポンプ１３等が駆動される。このため、１次温水
の全部又は一部が開閉弁１０をバイパスして２次
熱交換器１２を流れてから、冷却水戻り管７ａの
開閉弁１０より下流側を通過する。したがつて、
２次温水循環用ポンプ１３によつて温水配管１５
内を循環する水は、２次熱交換器１２を流れる１
次温水を第２次熱源として加熱されて２次温水と
なり、そしてこの２次温水は被加熱対象設備・機
器１４を加熱するものである。 On the other hand, the cooling water in the cooling water pipe 7 that has undergone heat exchange using the non-regenerative heat exchanger 5 as a primary heat source flows through the cooling water return pipe 7a as high-temperature return water (primary hot water). When there is no need to heat the equipment/equipment 14 to be heated, the on-off valve 10 is kept fully open, and the primary hot water passes through the cooling water return pipe 7a without flowing through the hot water supply system 11. . In addition, when heating the equipment/equipment 14 to be heated,
The on-off valve 10 is maintained in a fully closed state or an intermediate opening state, and the secondary hot water circulation pump 13 of the hot water supply system 11 and the like are driven. Therefore, all or part of the primary hot water bypasses the on-off valve 10 and flows through the secondary heat exchanger 12, and then passes through the cooling water return pipe 7a downstream of the on-off valve 10. Therefore,
Hot water piping 15 is connected by a secondary hot water circulation pump 13.
The water circulating inside the secondary heat exchanger 12 flows through the 1
The secondary hot water is heated as a secondary heat source to become secondary hot water, and this secondary hot water heats the equipment/equipment 14 to be heated.
このように、従来は発電所外に放出されるだけ
であつた原子炉冷却材浄化系２で得られた排熱を
有効に利用して、発電所内の換気空調系の暖房用
あるいは他の設備機器の加熱用としての温水を得
るから、従来大量に消費されていた重油焚きボイ
ラーの重油消費量を減らすことができ、発電所全
体としての省エネルギーが図れる。 In this way, the exhaust heat obtained from the reactor coolant purification system 2, which conventionally was only released outside the power plant, can be effectively used to heat the ventilation air conditioning system or other equipment inside the power plant. Since hot water is obtained for heating equipment, it is possible to reduce the amount of heavy oil consumed by heavy oil-fired boilers, which traditionally consumed a large amount, and the power plant as a whole can save energy.
なお、本実施例設備において、単位時間当り、
400m3／ｈの温水を温水配管１５に取り出し、被
加熱対象設備・機器１４にて例えば55℃の２次温
水を42℃に熱交換させたとすると、有効に利用さ
れる熱は
400m3／ｈ×（55℃−42℃）＝5.2×106Kcal／ｈ
である。これを従来方式のボイラ蒸気量相当に換
算すると、
蒸気量＝5.2×106Kcal／ｈ／571Kcal／ｈ＝10060Kg／
ｈ
である。この蒸気量の有効利用率を８ケ月／年、
負荷率35％として、年間のボイラ蒸気使用量の低
減量を求めると、
年間低減蒸気量＝10060・×24h×365×0.35×８／12×
１／1000＝20560ton／年
となる。そして、重油ボイラにて１Klの重油で得
られる蒸気量は12.7ton／Klであるから、重油の
節約量は間168Klとなる。 In addition, in the equipment of this example, per unit time,
Assuming that 400 m 3 /h of hot water is taken out to hot water piping 15 and the secondary hot water of, for example, 55°C is heat-exchanged to 42°C in heated equipment/equipment 14, the effectively used heat is 400 m 3 /h. ×(55°C−42°C)=5.2×10 6 Kcal/h. Converting this to the steam volume equivalent of a conventional boiler, steam volume = 5.2 x 10 6 Kcal/h/571Kcal/h = 10060Kg/
It is h. The effective utilization rate of this amount of steam is 8 months/year.
Assuming a load factor of 35%, the annual reduction in boiler steam usage is calculated as follows: Annual reduction in steam usage = 10060 x 24 h x 365 x 0.35 x 8/12 x
1/1000=20560ton/year. Since the amount of steam obtained from 1 Kl of heavy oil in a heavy oil boiler is 12.7 tons/Kl, the amount of heavy oil saved is 168 Kl.
すなわち、例えば年間3860Klの重油を使用する
原子力発電所において、従来に比べて約42％の重
油消費量となり、省エネルギー効果が充分に発揮
される。 That is, for example, in a nuclear power plant that uses 3860Kl of heavy oil per year, the fuel oil consumption will be approximately 42% compared to the conventional one, and the energy saving effect will be fully demonstrated.
また、被加熱対象設備・機器１４を加熱する１
次および２次温水は、その熱源として原子炉で得
られる排熱を利用するから、実際に発電タービン
等を駆動させる高温の熱循環系、すなわち原子炉
本来の機能には何ら悪影響を及ぼすことがない。
そして、１次温水を得る系つまり原子炉補機冷却
系（冷却水配管７等）は、１次温水を得る熱源と
なる原子炉冷却材浄化系２とは非再生熱交換器５
によつて隔離された別系統であり、さらに２次温
水を得る温水供給系１１は、上記原子炉補機冷却
系とは２次熱交換器によつて隔離された別系統で
ある。したがつて、このように２重に隔離された
相異なる系統により、２次温水を得て被加熱対象
設備・機器１４を加熱するから、放射化された不
純物を含む原子炉冷却材が、万が一にも被加熱対
象設備・機器１４を通して、これらが放射化され
ることがない。すなわち、原子炉冷却材浄化系２
を第１次熱源とし非再生熱交換器５を介して得た
１次温水を直接被加熱対象設備・機器１４に導く
ようにした場合は、万一、非再生熱交換器５の伝
熱管に孔があいてしまうと、放射化された不純物
を含む原子炉冷却材が被加熱対象設備・機器１４
に流れて被加熱対象設備・機器１４が放射能汚染
されることがあるが、上記のように被加熱対象設
備・機器１４に温水を導く温水供給系１１と原子
炉補機冷却材系とを２次熱交換器１２によつて隔
離しておけば、非再生熱交換器５の伝熱管に孔が
あいてしまつた場合でも、原子炉冷却材が温水供
給系１１に流れることはないから、被加熱対象設
備・機器１４の放射化を確実に防止して安全性を
完全なものとすることができる。 In addition, 1 which heats the equipment/equipment 14 to be heated
Since the secondary and secondary hot water uses the exhaust heat obtained from the nuclear reactor as its heat source, it will not have any adverse effect on the high-temperature thermal circulation system that actually drives the power generation turbine, etc., that is, on the original functions of the nuclear reactor. do not have.
The system for obtaining primary hot water, that is, the reactor auxiliary cooling system (cooling water piping 7, etc.) is different from the reactor coolant purification system 2, which is the heat source for obtaining primary hot water, and the non-regenerative heat exchanger 5.
Further, the hot water supply system 11 for obtaining secondary hot water is a separate system isolated from the reactor auxiliary equipment cooling system by a secondary heat exchanger. Therefore, since the secondary hot water is obtained through different systems that are doubly isolated in this way and heats the equipment/equipment 14 to be heated, reactor coolant containing activated impurities is However, these are not activated through the equipment/equipment 14 to be heated. That is, reactor coolant purification system 2
If the primary hot water obtained through the non-regenerative heat exchanger 5 is led directly to the equipment/equipment 14 to be heated, in the unlikely event that the heat exchanger tubes of the non-regenerative heat exchanger 5 If a hole opens, the reactor coolant containing radioactive impurities will be exposed to heated equipment/equipment 14.
However, as mentioned above, if the hot water supply system 11 that leads hot water to the heated equipment/equipment 14 and the reactor auxiliary equipment coolant system are If it is isolated by the secondary heat exchanger 12, even if the heat transfer tube of the non-regenerative heat exchanger 5 is punctured, the reactor coolant will not flow into the hot water supply system 11. It is possible to reliably prevent the radiation of the heated equipment/equipment 14 to ensure complete safety.
なお、本実施例の場合、非再生熱交換器５から
冷却水戻り管７ａに１次温水を得るようにしてお
り、非再生熱交換器５は本来冷却材を一定温度に
下げる機能を有しているから、安定した温度の１
次温水を簡単に得ることができる。 In the case of this embodiment, primary hot water is obtained from the non-regenerative heat exchanger 5 to the cooling water return pipe 7a, and the non-regenerative heat exchanger 5 originally has the function of lowering the coolant to a constant temperature. Because of this, the temperature is stable.
Next you can easily get hot water.
第３図は本発明の第２実施例を示している。こ
の第２実施例の基本的構成は第１実施例と同じで
あるから、対応する個所には同一符号を付して説
明は省略する。この第２実施例は、冷却水配管７
を閉ループとするとともに、この配管７に１次温
水循環用ポンプ１６を設けるとともに、原子炉補
機冷却系冷却水配管１７と熱交換して１次温水を
所定の温度まで冷却する熱交換器１８を設けた構
成以外は、第１実施例と同一構成である。 FIG. 3 shows a second embodiment of the invention. Since the basic configuration of the second embodiment is the same as that of the first embodiment, corresponding parts are denoted by the same reference numerals and a description thereof will be omitted. In this second embodiment, the cooling water pipe 7
This piping 7 is provided with a pump 16 for circulating primary hot water, and a heat exchanger 18 that exchanges heat with the cooling water piping 17 of the reactor auxiliary equipment cooling system to cool the primary hot water to a predetermined temperature. The configuration is the same as that of the first embodiment except for the configuration in which .
この第２実施例の場合は第１実施例と同様の作
用効果を得られることは勿論、１次温水がポンプ
１６によつて冷却水配管７を循環するから、第１
実施例に比してより高温の１次温水を得ることが
できるとともに、原子炉補機冷却水配管１７に対
しても２重の隔離がなされ、放射化された不純物
を含む原子炉冷却材が万が一にも上記冷却水配管
１７に流れることもない。 In the case of this second embodiment, not only can the same effects as in the first embodiment be obtained, but also because the primary hot water is circulated through the cooling water pipe 7 by the pump 16,
It is possible to obtain primary hot water with a higher temperature than in the example, and the reactor auxiliary cooling water piping 17 is also double isolated, so that reactor coolant containing activated impurities is removed. In any case, the cooling water does not flow into the cooling water pipe 17.
なお、上記各実施例図において被加熱対象設
備・機器は、１個のみを代表して描いたが、単数
の場合は勿論、直列又は並列にして複数用いても
よいことは言うまでもない。 In each of the above embodiment drawings, only one facility/device to be heated is depicted as a representative, but it goes without saying that a single device or a plurality of devices may be used in series or in parallel.
本発明は以上説明したように、原子炉冷却材浄
化系を流れる冷却材の排熱を採熱して温水を得る
温水供給系を設けたから、この温水供給系により
原子炉本来の熱循環系の機能に何ら悪影響を与え
ることなく、排熱を利用して被加熱対象設備・機
器を加熱でき、発電所内の省エネルギー化を実現
できる。そして、温水供給系は、原子炉冷却材浄
化系を第１次熱源としてこの第１次熱源から上記
原子炉冷却材浄化系の非再生熱交換器を介して１
次温水を得、この１次温水を第２次熱源として、
この第２次熱源から２次熱交換器を介して得た２
次温水を発電所内の所望の被加熱対象設備・機器
に導くようにしたから、原子炉冷却材浄化系と被
加熱対象設備・機器との間は非再生熱交換器と２
次熱交換器とにより２重に隔離され、よつて被加
熱対象設備・機器の放射化のおそれを確実に防止
できる等の効果を有する。 As explained above, the present invention provides a hot water supply system that obtains hot water by collecting exhaust heat from the coolant flowing through the reactor coolant purification system. The waste heat can be used to heat the equipment and equipment to be heated without any negative impact on the power plant, making it possible to save energy within the power plant. Then, the hot water supply system uses the reactor coolant purification system as a primary heat source, and from this primary heat source through the non-regenerative heat exchanger of the reactor coolant purification system.
Obtain secondary hot water and use this primary hot water as a secondary heat source,
2 obtained from this secondary heat source via a secondary heat exchanger
Since the next hot water is guided to the desired equipment and equipment to be heated within the power plant, there is a non-regenerative heat exchanger and two
It is doubly isolated by the secondary heat exchanger, and has the effect of reliably preventing the possibility of radiation of the equipment/equipment to be heated.
第１図は従来の原子炉冷却材浄化系を示す系統
図、第２図は本発明の第１実施例を示す原子炉発
電設備の冷却材浄化系および温水供給系の系統
図、第３図は本発明の第２実施例を示す同系統図
である。
１…原子炉圧力容器、２…原子炉冷却材浄化
系、４…再生熱交換器、５…非再生熱交換器、６
…浄化装置、７…冷却水配管、７ａ…冷却水戻り
管、１０…開閉弁、１１…温水供給系、１２…２
次熱交換器、１３…２次温水循環用ポンプ、１４
…被加熱対象設備・機器、１５…温水配管。
Fig. 1 is a system diagram showing a conventional reactor coolant purification system, Fig. 2 is a system diagram of a coolant purification system and hot water supply system of a nuclear power generation facility showing the first embodiment of the present invention, and Fig. 3 is a system diagram showing a conventional reactor coolant purification system. FIG. 2 is a system diagram showing a second embodiment of the present invention. 1... Reactor pressure vessel, 2... Reactor coolant purification system, 4... Regenerative heat exchanger, 5... Non-regenerative heat exchanger, 6
...Purification device, 7...Cooling water piping, 7a...Cooling water return pipe, 10...Opening/closing valve, 11...Hot water supply system, 12...2
Secondary heat exchanger, 13... Secondary hot water circulation pump, 14
...Equipment/equipment to be heated, 15...Hot water piping.
Claims (1)
する原子炉冷却材浄化系に、再生熱交換器と、冷
却材を所定の温度に下げる非再生熱交換器と、浄
化装置とを設けるとともに、この原子炉冷却材浄
化系を第１次熱源とし前記非再生熱交換器を介し
て得た１次温水を第２次熱源とし、この第２次熱
源から２次熱交換器を介して得られた２次温水を
発電所内の所望の被加熱対象設備・機器に導く温
水供給系を設けたことを特徴とする原子力発電設
備。 ２ 上記温水供給系は、２次温水を導く閉ループ
の温水配管に、２次温水循環用ポンプと、非再生
熱交換器における冷却水配管の冷却水戻り管の途
中に接続されて上記２次温水を加熱する２次熱交
換器と、被加熱対象設備・機器とを設けてなるこ
とを特徴とする特許請求の範囲第１項に記載の原
子力発電設備。[Scope of Claims] 1. A reactor coolant purification system that takes coolant out of the reactor pressure vessel and purifies it, includes a regenerative heat exchanger, a non-regenerative heat exchanger that lowers the coolant to a predetermined temperature, and a purification system. At the same time, this reactor coolant purification system is used as a primary heat source, the primary hot water obtained through the non-regenerative heat exchanger is used as a secondary heat source, and secondary heat exchange is performed from this secondary heat source. 1. Nuclear power generation equipment characterized by being provided with a hot water supply system that guides secondary hot water obtained through a reactor to desired heated target equipment/equipment within a power plant. 2. The hot water supply system is connected to a closed-loop hot water piping that introduces secondary hot water, a secondary hot water circulation pump, and a cooling water return pipe of the cooling water piping in the non-regenerative heat exchanger, and is connected to the closed loop hot water piping that leads the secondary hot water. The nuclear power generation facility according to claim 1, characterized in that it is provided with a secondary heat exchanger for heating the nuclear power plant and equipment/equipment to be heated.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56012691A JPS57125898A (en) | 1981-01-30 | 1981-01-30 | Atomic power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56012691A JPS57125898A (en) | 1981-01-30 | 1981-01-30 | Atomic power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57125898A JPS57125898A (en) | 1982-08-05 |
| JPH0252240B2 true JPH0252240B2 (en) | 1990-11-09 |
Family
ID=11812394
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56012691A Granted JPS57125898A (en) | 1981-01-30 | 1981-01-30 | Atomic power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57125898A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59112297A (en) * | 1982-12-18 | 1984-06-28 | 株式会社東芝 | Atomic power plant |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56119430A (en) * | 1980-02-25 | 1981-09-19 | Hitachi Ltd | Reactor building heating system |
| JPS5722595A (en) * | 1980-07-17 | 1982-02-05 | Tokyo Shibaura Electric Co | Atomic power facility |
-
1981
- 1981-01-30 JP JP56012691A patent/JPS57125898A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56119430A (en) * | 1980-02-25 | 1981-09-19 | Hitachi Ltd | Reactor building heating system |
| JPS5722595A (en) * | 1980-07-17 | 1982-02-05 | Tokyo Shibaura Electric Co | Atomic power facility |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57125898A (en) | 1982-08-05 |
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