JPH08160189A - In-plant hot water system equipment of reactor power plant - Google Patents
In-plant hot water system equipment of reactor power plantInfo
- Publication number
- JPH08160189A JPH08160189A JP6304892A JP30489294A JPH08160189A JP H08160189 A JPH08160189 A JP H08160189A JP 6304892 A JP6304892 A JP 6304892A JP 30489294 A JP30489294 A JP 30489294A JP H08160189 A JPH08160189 A JP H08160189A
- Authority
- JP
- Japan
- Prior art keywords
- hot water
- heat exchanger
- backup
- pipe
- steam
- 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
Landscapes
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は原子力発電所の所内温度
系設備に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a temperature system facility in a nuclear power plant.
【０００２】[0002]
【従来の技術】所内温度系設備は原子力発電所内の暖房
用温水を各空調機器（空調負荷）に対し供給する設備で
ある。図４により従来の原子力発電所の所内温度系設備
のプラント通常運転時について説明する。2. Description of the Related Art In-station temperature system equipment is equipment for supplying hot water for heating in a nuclear power plant to each air conditioner (air conditioning load). With reference to FIG. 4, a description will be given of a normal temperature operation of a conventional nuclear power plant temperature system facility during normal plant operation.
【０００３】プラント通常運転時、原子炉補機冷却系１
からは冷却水供給配管２を経て原子炉冷却材浄化系非再
生熱交換器３に原子炉補機冷却水（約35℃）を供給して
いる。原子炉冷却材浄化系非再生熱交換器３で原子炉水
と熱交換され、高温（60〜70℃程度）となった原子炉補
機冷却水は冷却水戻り配管４を経て温水熱交換器５へ導
かれる。During normal operation of the plant, the reactor auxiliary cooling system 1
Supplies the reactor auxiliary equipment cooling water (about 35 ° C.) to the reactor coolant purification system non-regenerative heat exchanger 3 through the cooling water supply pipe 2. The reactor auxiliary machine cooling water, which has been heated to a high temperature (about 60 to 70 ° C) by heat exchange with the reactor water in the reactor coolant non-regeneration heat exchanger 3, passes through the cooling water return pipe 4 to a hot water heat exchanger. Guided to 5.
【０００４】温水熱交換器５では原子炉補機冷却系の系
統水である冷却水供給配管２，原子炉冷却材浄化系非再
生熱交換器３，冷却水戻り配管４，温水熱交換器５を流
れる原子炉補機冷却水と熱交換を行う。In the hot water heat exchanger 5, a cooling water supply pipe 2, which is system water for the reactor auxiliary cooling system, a non-regenerative heat exchanger for the reactor coolant purification system 3, a cooling water return pipe 4, a hot water heat exchanger 5 Performs heat exchange with the reactor auxiliary equipment cooling water flowing through.
【０００５】高温となった所内温水は温水熱交換器出口
配管６，バックアップ熱交換器バイパス配管７，温水供
給配管８を経て原子力発電所内に点在する複数基の空調
負荷９へ供給し、所内暖房用の温水として用いる。The hot water in the plant, which has reached a high temperature, is supplied to a plurality of air conditioning loads 9 scattered in the nuclear power plant through a hot water heat exchanger outlet pipe 6, a backup heat exchanger bypass pipe 7, and a hot water supply pipe 8 to Used as hot water for heating.
【０００６】空調負荷９で熱交換された所内温水は所内
温水戻り配管10，所内温水ポンプ11，所内温水ポンプ出
口配管12，温水熱交換器入口配管13を経て再び温水熱交
換器５へ導かれる。[0006] The hot water in the office that has been heat-exchanged by the air conditioning load 9 is led again to the hot water heat exchanger 5 through the hot water return piping 10, the hot water pump 11, the hot water pump outlet piping 12, and the hot water heat exchanger inlet piping 13. .
【０００７】空調負荷９側が要求する温水供給温度は、
外気温度14により異なるが、その理由は、空調が施され
る室内温度は外気温度14に影響され、その室内の暖房に
必要な熱量の変動があることによる。図５に外気温度と
温水供給温度との関係を示す。このため、外気温度検出
点15で検出された外気温度14は温度調節器16で図５に示
す関係から温水供給温度を算出している。The hot water supply temperature required by the air conditioning load 9 side is
Although it depends on the outside air temperature 14, the reason is that the temperature inside the air-conditioned room is affected by the outside air temperature 14 and the amount of heat required for heating the room changes. FIG. 5 shows the relationship between the outside air temperature and the hot water supply temperature. Therefore, for the outside air temperature 14 detected at the outside air temperature detection point 15, the temperature controller 16 calculates the hot water supply temperature from the relationship shown in FIG.
【０００８】一方、温度供給温度検出点17で検出された
温水供給温度が算出された温水供給温度になるように温
水熱交換器出口配管６部に設けられた温度調整弁（高温
側）18および第２の温水熱交換器バイパス配管19に設け
られた温度調整弁（低温側）20の開度調整を行い、高温
流体と低温流体の混合比を変化させることにより行って
いる。On the other hand, a temperature control valve (high temperature side) 18 provided on the outlet pipe 6 of the hot water heat exchanger so that the hot water supply temperature detected at the temperature supply temperature detection point 17 becomes the calculated hot water supply temperature and The opening degree of the temperature control valve (low temperature side) 20 provided in the second hot water heat exchanger bypass pipe 19 is adjusted to change the mixing ratio of the high temperature fluid and the low temperature fluid.
【０００９】なお、本運転状態時、温水熱交換器入口弁
21およびバックアップ熱交換器バイパス弁22は開、なら
びにバックアップ熱交換器入口弁23，バックアップ熱交
換器所内蒸気入口弁30は閉とする。In this operating state, the hot water heat exchanger inlet valve
21 and the backup heat exchanger bypass valve 22 are opened, and the backup heat exchanger inlet valve 23 and the backup heat exchanger internal steam inlet valve 30 are closed.
【００１０】図６にプラント定検時の所内温水系設備の
構成を示す。図６は、図４の状態から温水熱交換器入口
弁21およびバックアップ熱交換器バイパス弁22を閉じ、
バックアップ熱交換器入口弁23およびバックアップ熱交
換器所内蒸気入口弁30を開となっている。FIG. 6 shows the construction of the hot water system facility in the plant at the time of regular plant inspection. 6 shows that the hot water heat exchanger inlet valve 21 and the backup heat exchanger bypass valve 22 are closed from the state of FIG.
The backup heat exchanger inlet valve 23 and the backup heat exchanger internal steam inlet valve 30 are open.
【００１１】プラント定検時には原子炉補機冷却系１か
らの高温流体の供給は受けられない。このため、バック
アップ熱交換器24を用い所内蒸気設備25からの所内蒸気
を熱源とした運転を行う。During the plant regular inspection, the high temperature fluid cannot be supplied from the reactor auxiliary cooling system 1. Therefore, the backup heat exchanger 24 is used to perform the operation using the in-house steam from the in-house steam facility 25 as a heat source.
【００１２】すなわち、所内温水は所内温水ポンプ出口
配管12，第１の温水熱交換器バイパス配管26，バックア
ップ熱交換器入口配管27を経てバックアップ熱交換器24
へ導かれる。バックアップ熱交換器24で所内蒸気と熱交
換された所内温水はバックアップ熱交換器出口配管28，
温水供給配管８を経て空調負荷９へ供給される。この
際，温水熱交換器入口弁21およびバックアップ熱交換器
バイパス弁22は閉およびバックアップ熱交換器入口弁23
は開状態とする。That is, the hot water in the plant is passed through the hot water pump outlet pipe 12, the first hot water heat exchanger bypass pipe 26, the backup heat exchanger inlet pipe 27, and the backup heat exchanger 24.
Be led to. The hot water in the plant that has exchanged heat with the steam in the plant by the backup heat exchanger 24 is the outlet pipe 28 of the backup heat exchanger.
It is supplied to the air conditioning load 9 through the hot water supply pipe 8. At this time, the hot water heat exchanger inlet valve 21 and the backup heat exchanger bypass valve 22 are closed and the backup heat exchanger inlet valve 23 is closed.
Is open.
【００１３】また温水供給温度の調整は温度調節器16か
らの信号により，バックアップ熱交換器所内蒸気入口配
管29に設けられたバックアップ熱交換器所内蒸気入口弁
30の開度を変化させバックアップ熱交換器24へ流入する
所内蒸気流量を調整することにより行う。Further, the hot water supply temperature is adjusted by a signal from the temperature controller 16 and a backup heat exchanger station steam inlet valve provided in the backup heat exchanger station steam inlet pipe 29.
This is done by changing the opening degree of 30 and adjusting the steam flow rate in the center flowing into the backup heat exchanger 24.
【００１４】一方、バックアップ熱交換器24へ流入した
所内蒸気はバックアップ熱交換器24胴内で熱交換し、凝
縮水となった後、バックアップ熱交換器所内蒸気出口配
管31およびバックアップ熱交換器24近傍に設けられた
（バックアップ熱交換器24と同一フロア43）蒸気トラッ
プ32，蒸気トラップ出口配管33を経て回収される。On the other hand, the in-house steam that has flowed into the backup heat exchanger 24 undergoes heat exchange in the body of the backup heat exchanger 24 to become condensed water, and then the backup heat exchanger inside steam outlet pipe 31 and the backup heat exchanger 24. It is recovered via a steam trap 32 and a steam trap outlet pipe 33 provided in the vicinity (on the same floor 43 as the backup heat exchanger 24).
【００１５】バックアップ熱交換器24の形式は一般的な
横置一胴型の多管式熱交換器であり、管側に所内温水が
（低温流体として）流れ、胴側に所内蒸気が（高温流体
として）流れるものである。The type of the backup heat exchanger 24 is a general horizontal single-tube multi-tube heat exchanger, in which hot water in the plant flows (as a low-temperature fluid) to the pipe side and steam in the plant (high temperature One that flows (as a fluid).
【００１６】[0016]
【発明が解決しようとする課題】所内温水系設備のプラ
ント定検時の運転に関し、外気温度が比較的高い中間期
等においては、空調負荷９への温水供給温度は低下して
くる。すなわち、熱負荷は減少してくる。このため、バ
ックアップ熱交換器24へ流入する所内蒸気流量もバック
アップ熱交換器所内蒸気入口弁30が絞りこまれることに
より減少する。Regarding the operation of the in-house hot water system equipment during the plant regular inspection, the hot water supply temperature to the air conditioning load 9 decreases during the intermediate period when the outside air temperature is relatively high. That is, the heat load decreases. Therefore, the in-house steam flow rate flowing into the backup heat exchanger 24 is also reduced by narrowing down the in-house steam inlet valve 30 of the backup heat exchanger.
【００１７】バックアップ熱交換器24に流入した所内蒸
気はバックアップ熱交換器24管側を流れる所内温水と熱
交換し凝縮するが、所内蒸気流量が少なく、またバック
アップ熱交換器24温水出口温度（温水供給温度）も低い
ため、この凝縮水はさらに（水−水熱交換による）冷却
が行われる“過冷却”状態となり、この結果、バックア
ップ熱交換器24胴内雰囲気温度は低くなる。The in-plant steam that has flowed into the backup heat exchanger 24 exchanges heat with the in-plant hot water flowing through the pipe side of the backup heat exchanger 24 and condenses, but the in-plant steam flow rate is low, and the backup heat exchanger 24 hot water outlet temperature (hot water Since the supply temperature is also low, this condensed water is in a “supercooled” state in which it is further cooled (by water-water heat exchange), and as a result, the ambient temperature inside the backup heat exchanger 24 becomes low.
【００１８】バックアップ熱交換器24の胴内圧力は、胴
内雰囲気温度に相当する飽和蒸気圧となることから、胴
内雰囲気温度の低下に伴い胴内圧力も低くなり、胴内雰
囲気温度 100℃以下の場合負荷になり得る。Since the in-cylinder pressure of the backup heat exchanger 24 becomes a saturated vapor pressure corresponding to the in-cylinder atmosphere temperature, the in-cylinder pressure also decreases as the in-cylinder atmosphere temperature decreases, and the in-cylinder atmosphere temperature becomes 100 ° C. It can be a load in the following cases.
【００１９】この凝縮水はバックアップ熱交換器24から
連続的に排出されるが、一方、バックアップ熱交換器24
の胴内圧力が低下しているため、蒸気トラップ32の入口
部における圧力も同様に低下する。蒸気トラップ32の出
口部の圧力は一般的には大気圧程度となっているため、
蒸気トラップ32の入口部と出口部における圧力の大小関
係は出口部＞入口部となる。This condensed water is continuously discharged from the backup heat exchanger 24, while the backup heat exchanger 24 is discharged.
Since the in-body pressure of is reduced, the pressure at the inlet of the steam trap 32 is also reduced. Since the pressure at the outlet of the steam trap 32 is generally about atmospheric pressure,
The magnitude relationship between the pressures at the inlet and outlet of the steam trap 32 is outlet> inlet.
【００２０】蒸気トラップ32は構造上入口部圧力＞出口
部圧力となると、入口側から出口側への流路が確保され
凝縮水を出口側へ排出する原理となっているため、上記
圧力の大小関係の場合、凝縮水を排出できないこととな
る。Due to the structure of the steam trap 32, when the inlet pressure> the outlet pressure, the principle is that a flow path from the inlet side to the outlet side is secured and condensed water is discharged to the outlet side. In the case of a relationship, the condensed water cannot be discharged.
【００２１】これによりバックアップ熱交換器24から排
出された凝縮水は、徐々に蒸気トラップ32上流側のバッ
クアップ熱交換器所内蒸気出口配管31内に停滞し、最終
的にはバックアップ熱交換器24胴内にまで残留する。As a result, the condensed water discharged from the backup heat exchanger 24 gradually stagnates in the steam outlet pipe 31 in the backup heat exchanger in the upstream side of the steam trap 32, and finally in the body of the backup heat exchanger 24. It remains inside.
【００２２】バックアップ熱交換器24胴内に残留した凝
縮水は蒸気トラップ32の排出能力に見合うある水位レベ
ルまでバランスする。凝縮水が蒸気トラップ32上流側に
残留することにより、残留した凝縮水の水頭差分の圧力
が蒸気トラップ32の入口部圧力に加えられ、この結果、
入口部圧力＞出口部圧力となると蒸気トラップ32からの
凝縮水の排出が行われる。The condensed water remaining inside the backup heat exchanger 24 balances to a certain water level level commensurate with the discharge capacity of the steam trap 32. Since the condensed water remains on the upstream side of the steam trap 32, the pressure of the residual head difference of the condensed water is added to the inlet pressure of the steam trap 32, and as a result,
When the inlet pressure> the outlet pressure, the condensed water is discharged from the steam trap 32.
【００２３】このようにバックアップ熱交換器24を用
い、温水供給温度が低く、かつ所内蒸気流量が少ない場
合の運転においては、凝縮水がバックアップ熱交換器24
胴内に残留する場合がある。バックアップ熱交換器24胴
内に凝縮水が残留することはバックアップ熱交換器24本
来の蒸気凝縮器としての運転方法から逸脱するもので、
回避しなければならない課題がある。As described above, when the backup heat exchanger 24 is used and the hot water supply temperature is low and the steam flow rate in the plant is small, the condensed water is the backup heat exchanger 24.
May remain in the trunk. The fact that condensed water remains in the backup heat exchanger 24 barrel deviates from the operation method as the original steam condenser of the backup heat exchanger 24.
There are challenges that must be avoided.
【００２４】また、バックアップ熱交換器24の胴内に凝
縮水が残留することは流入してくる所内蒸気の不安定凝
縮の要因にもなり、このため異音・振動の発生の可能性
もあることにより、同様に回避しなければならない課題
がある。In addition, the fact that condensed water remains in the body of the backup heat exchanger 24 also causes unstable condensation of the in-house steam that flows in, which may cause abnormal noise and vibration. Therefore, there is a problem that must be avoided as well.
【００２５】本発明は上記課題を解決するためになされ
たもので、外気温度が比較的高い中間器の運転において
も（バックアップ熱交換器24を底流量の所内蒸気で運転
した場合においても）バックアップ熱交換器24の胴内に
凝縮水が残留しないようにし、しかも流入する所内蒸気
の不安定凝縮の発生の可能性を回避できるようにした原
子力発電所の所内温水系設備を提供することにある。The present invention has been made in order to solve the above-mentioned problems, and it is backed up even in the operation of an intermediate device having a relatively high outside air temperature (even when the backup heat exchanger 24 is operated with the in-house steam having a bottom flow rate). It is an object of the present invention to provide an on-site hot water system facility of a nuclear power plant, which prevents condensed water from remaining in the body of the heat exchanger 24 and can avoid the possibility of unstable condensation of inflowing in-house steam. .
【００２６】[0026]
【課題を解決するための手段】第１の発明は原子炉補機
冷却系から冷却水供給配管を経て原子炉冷却材浄化系非
再生熱交換器に補機冷却水を供給し、原子炉水と熱交換
された原子炉補機冷却水を冷却水戻り配管を経て温水熱
交換器へ導き、この温水熱交換器で高温となった所内温
水を温水熱交換器出口配管からバックアップ熱交換器バ
イパス配管および温水供給配管を経て空調負荷へ供給
し、この空調負荷で熱交換された所内温水を所内温水戻
り配管を経て所内温水ポンプにより所内温水ポンプ出口
配管を経て前記温水熱交換器へ導く前記温水熱交換器か
ら前記空調負荷への系統と、所内蒸気設備からの所内蒸
気をバックアップ熱交換器へ導き、このバックアップ熱
交換器で所内蒸気として熱交換された所内温水をバック
アップ熱交換器出口配管から前記温水供給配管を経て前
記空調負荷へ供給し、前記バックアップ熱交換器へ前記
所内温水出口ポンプ出口配管から第１の温水熱交換器バ
イパス配管を経て温水を導く前記バックアップ熱交換器
から前記空調負荷への系統を備えた原子力発電所の所内
温水系設備において、前記空調負荷と前記温水供給配管
との間に温水供給流量調整弁を設け、この温水供給流量
調整弁と前記空調負荷とを温度検出器および温度調節器
で電気的に接続し、前記温水供給配管と前記所内温水戻
り配管との間にバイパス流量調整弁を有する所内温度バ
イパス配管を接続し、前記所内温水ポンプの吐出側に流
量検出器および流量調節器を直列接続し、この流量調節
器と前記温水供給流量調整弁とを電気的に接続してなる
ことを特徴とする。A first aspect of the present invention is to supply auxiliary cooling water from a reactor auxiliary cooling system to a reactor coolant purification system non-regenerative heat exchanger through a cooling water supply pipe. The reactor auxiliary equipment cooling water that has undergone heat exchange with the hot water heat exchanger is guided to the hot water heat exchanger via the cooling water return pipe, and the hot water inside the plant that has become hot in this hot water heat exchanger is backed up from the hot water heat exchanger outlet pipe The hot water that is supplied to the air conditioning load via the piping and the hot water supply pipe, and the hot water that has been heat-exchanged by the air conditioning load is guided to the hot water heat exchanger via the hot water pump outlet pipe by the hot water pump via the hot water return pipe The system from the heat exchanger to the air conditioning load and the in-house steam from the in-house steam facility are guided to the backup heat exchanger, and the in-house hot water that has undergone heat exchange as in-house steam in this backup heat exchanger is the outlet of the backup heat exchanger. Supply from the pipe to the air conditioning load through the hot water supply pipe, and guide the hot water to the backup heat exchanger from the in-house hot water outlet pump outlet pipe through the first hot water heat exchanger bypass pipe to the backup heat exchanger. In a hot water system facility in a nuclear power plant equipped with a system for an air conditioning load, a hot water supply flow rate adjusting valve is provided between the air conditioning load and the hot water supply pipe, and the hot water supply flow rate adjusting valve and the air conditioning load are connected to each other. Electrically connected with a temperature detector and a temperature controller, connect the in-house temperature bypass pipe having a bypass flow rate adjusting valve between the hot water supply pipe and the in-house hot water return pipe, and connect to the discharge side of the in-house hot water pump. A flow rate detector and a flow rate controller are connected in series, and the flow rate controller and the hot water supply flow rate adjusting valve are electrically connected.
【００２７】第２の発明は原子炉補機冷却系から冷却水
供給配管を経て原子炉冷却材浄化系非再生熱交換器に補
機冷却水を供給し、原子炉水と熱交換された原子炉補機
冷却水を冷却水戻り配管を経て温水熱交換器へ導き、こ
の温水熱交換器で高温となった所内温水を温水熱交換器
出口配管からバックアップ熱交換器バイパス配管および
温水供給配管を経て空調負荷へ供給し、この空調負荷で
熱交換された所内温水を所内温水戻り配管を経て所内温
水ポンプにより所内温水ポンプ出口配管を経て前記温水
熱交換器へ導く前記温水熱交換器から前記空調負荷への
系統と、所内蒸気設備からの所内蒸気をバックアップ熱
交換器へ導き、このバックアップ熱交換器で所内蒸気と
して熱交換された所内温水をバックアップ熱交換器出口
配管から前記温水供給配管を経て前記空調負荷へ供給
し、前記バックアップ熱交換器へ前記所内温水出口ポン
プ出口配管から第１の温水熱交換器バイパス配管を経て
温水を導く前記バックアップ熱交換器から前記空調負荷
への系統を備えた原子力発電所の所内温水系設備におい
て、前記バックアップ熱交換器出口配管に温度検出器お
よび温度調節器を直列接続し、前記温度調節器と前記バ
ックアップ熱交換器所内蒸気入口弁とを電気的に接続し
てなることを特徴とする。A second aspect of the invention is to supply the auxiliary machine cooling water from the reactor auxiliary machine cooling system to the non-regenerative heat exchanger of the reactor coolant purifying system through the cooling water supply pipe, and to exchange atoms with the reactor water. The reactor auxiliary equipment cooling water is led to the hot water heat exchanger through the cooling water return pipe, and the hot water in the plant heated to a high temperature in this hot water heat exchanger is fed from the hot water heat exchanger outlet pipe to the backup heat exchanger bypass pipe and hot water supply pipe. Through the in-house hot water pump through the in-house hot water return pipe to the in-house hot water pump outlet pipe to the hot water heat exchanger. The system to the load and the in-house steam from the in-house steam facility are guided to the backup heat exchanger, and the in-house hot water that has undergone heat exchange as in-house steam in this backup heat exchanger is transferred to the hot water from the backup heat exchanger outlet pipe. Supply from the backup heat exchanger to the air conditioning load, which is supplied to the air conditioning load via the supply pipe and guides hot water to the backup heat exchanger from the in-house hot water outlet pump outlet pipe through the first hot water heat exchanger bypass pipe. In a hot water system facility of a nuclear power plant equipped with a system, a temperature detector and a temperature controller are connected in series to the backup heat exchanger outlet pipe, and the temperature controller and the backup heat exchanger station steam inlet valve are connected. It is characterized by being electrically connected.
【００２８】第３の発明は原子炉補機冷却系から冷却水
供給配管を経て原子炉冷却材浄化系非再生熱交換器に補
機冷却水を供給し、原子炉水と熱交換された原子炉補機
冷却水を冷却水戻り配管を経て温水熱交換器へ導き、こ
の温水熱交換器で高温となった所内温水を温水熱交換器
出口配管からバックアップ熱交換器バイパス配管および
温水供給配管を経て空調負荷へ供給し、この空調負荷で
熱交換された所内温水を所内温水戻り配管を経て所内温
水ポンプにより所内温水ポンプ出口配管を経て前記温水
熱交換器へ導く前記温水熱交換器から前記空調負荷への
系統と、所内蒸気設備からの所内蒸気をバックアップ熱
交換器へ導き、このバックアップ熱交換器で所内蒸気と
して熱交換された所内温水をバックアップ熱交換器出口
配管から前記温水供給配管を経て前記空調負荷へ供給
し、前記バックアップ熱交換器へ前記所内温水出口ポン
プ出口配管から第１の温水熱交換器バイパス配管を経て
温水を導く前記バックアップ熱交換器から前記空調負荷
への系統を備えた原子力発電所の所内温水系設備におい
て、前記バックアップ熱交換器にバックアップ熱交換器
所内蒸気出口配管を前記バックアップ熱交換器を設置し
た設置フロアより階下フロアにまで延長して接続し、こ
のバックアップ熱交換器所内蒸気出口配管に蒸気トラッ
プを接続し、この蒸気トラップに蒸気トラップ出口配管
を接続し、この蒸気トラップ出口配管を前記階下フロア
よりさらに下方へ延長してなることを特徴とする。A third aspect of the invention is to supply the auxiliary machine cooling water from the reactor auxiliary machine cooling system to the non-regenerative heat exchanger of the reactor coolant purification system through the cooling water supply pipe, and to exchange atoms with the reactor water. The reactor auxiliary equipment cooling water is led to the hot water heat exchanger through the cooling water return pipe, and the hot water in the plant heated to a high temperature in this hot water heat exchanger is fed from the hot water heat exchanger outlet pipe to the backup heat exchanger bypass pipe and hot water supply pipe. Through the in-house hot water pump through the in-house hot water return pipe to the in-house hot water pump outlet pipe to the hot water heat exchanger. The system to the load and the in-house steam from the in-house steam facility are guided to the backup heat exchanger, and the in-house hot water that has undergone heat exchange as in-house steam in this backup heat exchanger is transferred to the hot water from the backup heat exchanger outlet pipe. Supply from the backup heat exchanger to the air conditioning load, which is supplied to the air conditioning load via the supply pipe and guides hot water to the backup heat exchanger from the in-house hot water outlet pump outlet pipe through the first hot water heat exchanger bypass pipe. In a hot water system facility of a nuclear power plant equipped with a system, the backup heat exchanger is connected by extending the backup heat exchanger in-house steam outlet pipe from the installation floor where the backup heat exchanger is installed to the floor below. A steam trap is connected to the steam outlet pipe in the backup heat exchanger station, a steam trap outlet pipe is connected to the steam trap, and the steam trap outlet pipe is extended further below the downstairs floor. .
【００２９】[0029]
【作用】第１の発明において、中間期等、空調熱負荷が
少ない時期に、バックアップ熱交換器を用いた運転を行
う際、バックアップ熱交換器の上記供給流量は定格流量
に対し減少するが、空調負荷に温度検出器と温度調整器
を設けて温水出口温度を高く設定し、温水供給流量調整
弁により温水供給流量を調整する。これにより、バック
アップ熱交換器の胴内に凝縮水が残留することを回避で
きる。In the first aspect of the invention, when the backup heat exchanger is operated at a time when the air-conditioning heat load is small, such as in the middle period, the above-mentioned supply flow rate of the backup heat exchanger decreases from the rated flow rate. A temperature detector and a temperature controller are installed in the air conditioning load to set the hot water outlet temperature high, and the hot water supply flow rate adjustment valve adjusts the hot water supply flow rate. As a result, it is possible to prevent condensed water from remaining in the body of the backup heat exchanger.
【００３０】第２の発明において、中間期等、空調熱負
荷が少ない時期に、バックアップ熱交換器を用いた運転
を行う際、バックアップ熱交換器への蒸気供給流量およ
び温水流量は減少するが、バックアップ熱交換器所内蒸
気入口弁と高温側温度調整弁との間に温度検出器と温度
調節器を設け、温水出口温度を高く設定する。これによ
りバックアップ熱交換器の胴内に凝縮水が残留すること
を回避できる。In the second aspect of the invention, when the operation using the backup heat exchanger is performed at a time when the air conditioning heat load is small, such as in the intermediate period, the steam supply flow rate and the hot water flow rate to the backup heat exchanger decrease, A temperature detector and temperature controller are installed between the steam inlet valve in the backup heat exchanger and the high temperature side temperature adjusting valve to set the hot water outlet temperature high. As a result, it is possible to avoid the condensed water from remaining in the body of the backup heat exchanger.
【００３１】第３の発明において、中間期等、空調熱負
荷が少ない時期に、バックアップ熱交換器を用いた運転
を行う際、バックアップ熱交換器への蒸気供給流量は減
少するが、場合によっては温水流量も減少する。In the third aspect of the present invention, when the operation using the backup heat exchanger is performed at a time when the air conditioning heat load is small, such as in the intermediate period, the steam supply flow rate to the backup heat exchanger decreases, but in some cases, The hot water flow rate also decreases.
【００３２】バックアップ熱交換器の胴体出口側配管部
に設置される蒸気トラップをバックアップ熱交換器より
も所内温水戻り配管10ｍ程度下部の階下フロアに配置す
ることによりバックアップ熱交換器の胴内に凝縮水が残
留することを回避できる。By condensing the steam trap, which is installed on the body outlet side piping of the backup heat exchanger, on the lower floor of the backup heat exchanger about 10 m below the hot water return pipe in the plant, it is condensed in the body of the backup heat exchanger. Water can be prevented from remaining.
【００３３】[0033]
【実施例】図１により本発明に係る原子力発電所の所内
温水系設備の第１の実施例を説明する。なお、図１中、
図４と同一部分には同一符号を付している。図１におい
て、原子炉補機冷却系１は冷却水供給配管２を介して原
子炉冷却材浄化系非再生熱交換器３に接続している。原
子炉冷却材浄化系非再生熱交換器３は冷却水戻り配管４
により温水熱交換器５に接続している。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of the hot water system facility in a nuclear power plant according to the present invention will be described with reference to FIG. In addition, in FIG.
The same parts as those in FIG. 4 are designated by the same reference numerals. In FIG. 1, the reactor auxiliary equipment cooling system 1 is connected to a reactor coolant purification system non-regenerative heat exchanger 3 via a cooling water supply pipe 2. Reactor coolant purification system non-regenerative heat exchanger 3 is cooling water return pipe 4
Is connected to the hot water heat exchanger 5.
【００３４】温水熱交換器５で熱交換し冷却した冷却水
は原子炉水として原子炉へ供給される。温水熱交換器５
に接続した温水熱交換器出口配管６は温水供給配管８に
接続し、温水供給配管８には温水供給流量調整弁36が設
けられ、この温水供給流量調整弁36の出口側に空調負荷
９が接続している。空調負荷９には温度検出器34と温度
調節器35が設けられ、これらは電気的に接続し、温度調
節器35は温水供給流量調整弁36に電気的に接続してい
る。The cooling water that has undergone heat exchange in the hot water heat exchanger 5 and is cooled is supplied to the reactor as reactor water. Hot water heat exchanger 5
The hot water heat exchanger outlet pipe 6 connected to is connected to the hot water supply pipe 8, the hot water supply pipe 8 is provided with a hot water supply flow rate adjusting valve 36, and the air conditioning load 9 is provided on the outlet side of the hot water supply flow rate adjusting valve 36. Connected. The air conditioning load 9 is provided with a temperature detector 34 and a temperature controller 35, which are electrically connected to each other, and the temperature controller 35 is electrically connected to a hot water supply flow rate adjusting valve 36.
【００３５】空調負荷９は所内温水戻り配管10を接続
し、所内温水戻り配管10の下流側は所内温水ポンプ11，
所内温水ポンプ出口配管12，温水熱交換器入口配管13お
よび温水熱交換器入口弁21が接続し、温水熱交換器入口
弁21は温水熱交換器５に接続している。The air conditioning load 9 is connected to a hot water return pipe 10 in the plant, and the hot water pump 11 for the plant is provided on the downstream side of the hot water return pipe 10 for the plant.
The in-house hot water pump outlet pipe 12, the hot water heat exchanger inlet pipe 13 and the hot water heat exchanger inlet valve 21 are connected, and the hot water heat exchanger inlet valve 21 is connected to the hot water heat exchanger 5.
【００３６】所内温水ポンプ11と所内温水ポンプ出口配
管12の間には流量検出器37と流量調節器38が接続し、流
量調節器38は温水熱交換器出口配管６と所内温水戻り配
管10との間に設けた所内温水バイパス配管39の所内温水
バイパス流量調整弁40に電気的に接続している。A flow rate detector 37 and a flow rate controller 38 are connected between the on-site hot water pump 11 and the on-site hot water pump outlet pipe 12, and the flow rate controller 38 includes the hot water heat exchanger outlet pipe 6 and the on-site hot water return pipe 10. The in-house hot water bypass pipe 39 is electrically connected to the in-house hot water bypass flow rate adjusting valve 40.
【００３７】所内温水ポンプ出口配管12から分岐して第
１の温水熱交換器バイパス配管26が接続し、第１の温水
熱交換器バイパス配管26はバックアップ熱交換器入口配
管27およびバックアップ熱交換器入口弁23を介してバッ
クアップ熱交換器24に接続している。The first hot water heat exchanger bypass pipe 26 branches off from the in-house hot water pump outlet pipe 12, and the first hot water heat exchanger bypass pipe 26 is a backup heat exchanger inlet pipe 27 and a backup heat exchanger. It is connected to a backup heat exchanger 24 via an inlet valve 23.
【００３８】バックアップ熱交換器24にはバックアップ
熱交換器出口配管28とバックアップ熱交換器所内蒸気入
口配管29およびバックアップ熱交換器所内蒸気出口配管
31が接続し、バックアップ熱交換器出口配管28は温水熱
交換器出口配管６に接続している。The backup heat exchanger 24 includes a backup heat exchanger outlet pipe 28, a backup heat exchanger station steam inlet pipe 29, and a backup heat exchanger station steam outlet pipe.
31 is connected, and the backup heat exchanger outlet pipe 28 is connected to the hot water heat exchanger outlet pipe 6.
【００３９】バックアップ熱交換器所内蒸気入口配管29
はバックアップ熱交換器所内蒸気入口弁30を介して所内
蒸気設備25に接続し、バックアップ熱交換器所内蒸気出
口配管31は蒸気トラップ32に接続し、蒸気トラップ32は
フロア43を貫通した蒸気トラップ出口配管33を接続して
いる。[0039] Steam inlet piping 29 in the backup heat exchanger station
Is connected to the in-house steam facility 25 via the steam inlet valve 30 in the backup heat exchanger, the steam outlet pipe 31 in the backup heat exchanger is connected to the steam trap 32, and the steam trap 32 is a steam trap outlet penetrating the floor 43. The pipe 33 is connected.
【００４０】バックアップ熱交換器所内蒸気入口弁30は
温度調節器16と電気的に接続している。温度調節器16は
温度供給温度検出点17に電気的に接続し、温度供給温度
検出点17は温水供給配管８に接続している。The steam inlet valve 30 in the backup heat exchanger station is electrically connected to the temperature controller 16. The temperature controller 16 is electrically connected to the temperature supply temperature detection point 17, and the temperature supply temperature detection point 17 is connected to the hot water supply pipe 8.
【００４１】しかして、第１の実施例によれば温度調節
器16で設定する温水供給温度は外気温度によらず例えば
60℃以上のある一定値とする。この場合、空調負荷９へ
の温水供給温度は中間等においては必要以上に高くなる
ことが起こり得る。However, according to the first embodiment, the hot water supply temperature set by the temperature controller 16 does not depend on the outside air temperature, for example,
Set to a certain value of 60 ℃ or higher. In this case, the temperature of the hot water supplied to the air conditioning load 9 may be unnecessarily high in the middle or the like.
【００４２】このため、空調負荷９ごとに温度検出器34
および温度調節器35を設け温水供給流量調整弁36で温水
供給流量を調整することにより所内の熱負荷を確保す
る。一方、空調負荷９における熱負荷が減少すると温水
供給流量調整弁36が絞られ、所内温水ポンプ11は締切運
転に近くなる場合もおこる。Therefore, the temperature detector 34 is provided for each air conditioning load 9.
And the temperature controller 35 is provided to adjust the hot water supply flow rate by the hot water supply flow rate adjusting valve 36 to secure the heat load in the plant. On the other hand, when the heat load in the air conditioning load 9 decreases, the hot water supply flow rate adjusting valve 36 is throttled, and the in-house hot water pump 11 may approach the deadline operation.
【００４３】そこで、所内温水ポンプ出口配管12部に流
量検出器37および流量調節器38を設け、所内温水バイパ
ス配管39部の所内温水バイパス流量調整弁40の開度を調
整し、常に一定の所内温水ポンプ11の吐出流量とする。Therefore, a flow rate detector 37 and a flow rate controller 38 are provided at the outlet pipe 12 of the in-house hot water pump, and the opening degree of the in-house hot water bypass flow adjusting valve 40 in the in-house hot water bypass pipe 39 is adjusted to keep a constant in-house It is the discharge flow rate of the hot water pump 11.
【００４４】この結果、中間期等の運転でバックアップ
熱交換器24へ流入する所内蒸気流量が減少し、前述した
所内蒸気の“過冷却”状態が発生してもバックアップ熱
交換器24の管側出口温度（すなわち、温水供給温度）
は、従来よりも高いため、バックアップ熱交換器24の胴
内雰囲気温度を高くすることが可能となる。As a result, the steam flow rate to the backup heat exchanger 24 during the operation in the intermediate period decreases, and even if the above-mentioned "supercooling" state of the steam occurs, the pipe side of the backup heat exchanger 24 Outlet temperature (ie hot water supply temperature)
Is higher than that of the conventional case, so that the ambient temperature inside the body of the backup heat exchanger 24 can be increased.
【００４５】バックアップ熱交換器24の胴内雰囲気温度
が高ければ、その胴内圧力を正圧に維持することが可能
となり、蒸気トラップ32における凝縮水の排出も十分に
できるため、バックアップ熱交換器24の胴内への凝縮水
の残留を回避することができる。If the ambient temperature inside the backup heat exchanger 24 is high, the internal pressure of the backup heat exchanger 24 can be maintained at a positive pressure and the condensed water in the steam trap 32 can be sufficiently discharged. It is possible to prevent the condensed water from remaining in the body of 24.
【００４６】つぎに図２により本発明に係る原子力発電
所の所内温水系設備の第２の実施例を説明する。図２中
図１と同一部分には同一符号を付して重複する部分の説
明は省略し、要部のみ説明する。Next, a second embodiment of the hot water system facility in the nuclear power plant according to the present invention will be described with reference to FIG. 2, those parts which are the same as those corresponding parts in FIG. 1 are designated by the same reference numerals, and a description of the overlapping parts will be omitted. Only the essential parts will be described.
【００４７】本第２の実施例はバックアップ熱交換器24
のバックアップ熱交換器出口配管28部に温度検出器41お
よび温度調節器42を設け、温度調節器42をバックアップ
熱交換器所内蒸気入口弁30と電気的に接続しており、そ
の他の部分は図１に示した部分と同一なので省略してい
る。The second embodiment is a backup heat exchanger 24.
A temperature detector 41 and a temperature controller 42 are provided in the backup heat exchanger outlet pipe 28 of the temperature controller 42, and the temperature controller 42 is electrically connected to the backup heat exchanger internal steam inlet valve 30. Since it is the same as the part shown in 1, it is omitted.
【００４８】バックアップ熱交換器24の管側出口の所内
温水温度は外気温度によらず、ある一定値（例えば60
℃）以上とする。なお、空調負荷９への温水供給温度の
調整はバックアップ熱交換器出口配管28部に設けられた
温度調整弁（高温側）18および温水温水熱交換器出口配
管６部に設けられた温度調整弁（低温側）20の開度調整
により行う。The hot water temperature at the outlet of the backup heat exchanger 24 on the pipe side does not depend on the outside air temperature, but has a certain value (for example, 60
℃) or more. The temperature of hot water supplied to the air conditioning load 9 is adjusted by the temperature control valve (high temperature side) 18 provided at the outlet pipe 28 of the backup heat exchanger and the temperature control valve provided at the outlet pipe 6 of the hot water hot water heat exchanger. (Low temperature side) Adjust by opening 20.
【００４９】この第２の実施例によれば第１の実施例と
同様にバックアップ熱交換器24の胴内圧力を正圧に維持
でき、その胴内への凝縮水の残留を回避できる。According to the second embodiment, the internal pressure of the backup heat exchanger 24 can be maintained at a positive pressure as in the first embodiment, and it is possible to prevent the condensed water from remaining in the internal cylinder.
【００５０】つぎに図３により本発明に係る原子力発電
所の所内温水系設備の第３の実施例を説明する。図３
中、図１と同一部分には同一符号を付して重複する部分
の説明は省略し、要部のみ説明する。この第３の実施例
においては、従来バックアップ熱交換器24と同一のフロ
ア43に設置されていた蒸気トラップ32をバックアップ熱
交換器24よりも10ｍ程度下部の階下フロア44へ設置する
ことにある。蒸気トラップ32の蒸気トラップ出口配管33
は階下フロア44を貫通している。その他の部分は図４に
示した従来例と同様であるので、その説明は省略する。Next, referring to FIG. 3, a third embodiment of the hot water system facility in the nuclear power plant according to the present invention will be described. FIG.
In FIG. 1, the same parts as those in FIG. 1 are designated by the same reference numerals, and the description of the overlapping parts will be omitted. In the third embodiment, the steam trap 32, which was conventionally installed on the same floor 43 as the backup heat exchanger 24, is installed on the lower floor 44 about 10 m below the backup heat exchanger 24. Steam trap 32 steam trap outlet pipe 33
Penetrates downstairs floor 44. The other parts are the same as those of the conventional example shown in FIG.
【００５１】この第３の実施例によれば、バックアップ
熱交換器24の胴内が負圧となり、蒸気トラップ32での凝
縮水の排出ができなくなり、凝縮水が蒸気トラップ32の
上流側のバックアップ熱交換器所内蒸気出口配管31部に
停滞しても、水頭差として10ｍ程度が確保されていれ
ば、凝縮水がバックアップ熱交換器24の胴内に残留する
前に必ず蒸気トラップ32の入口部圧力＞出口部圧力の関
係が成立し凝縮水は排出される。According to the third embodiment, the inside of the shell of the backup heat exchanger 24 has a negative pressure, the condensed water cannot be discharged from the steam trap 32, and the condensed water is backed up on the upstream side of the steam trap 32. Even if the steam outlet pipe 31 in the heat exchanger is stagnant, if the head difference is about 10 m, the inlet of the steam trap 32 must be kept before the condensed water remains in the body of the backup heat exchanger 24. The relationship of pressure> outlet pressure is established, and the condensed water is discharged.
【００５２】その理由は例えバックアップ熱交換器24の
胴側が真空となっても水頭が10ｍで大気圧と等しくなる
ので、大気圧によって凝縮水が押戻されることなく、従
って胴側に凝縮水が残留することはないからである。し
たがって、第３の実施例において、凝縮水はバックアッ
プ熱交換器所内蒸気出口配管31部に停滞することはあっ
てもバックアップ熱交換器24の胴内に残留することはな
い。The reason is that even if the cylinder side of the backup heat exchanger 24 is in a vacuum, the water head is equal to the atmospheric pressure at 10 m, so that the condensed water is not pushed back by the atmospheric pressure, so that the condensed water is kept on the cylinder side. This is because it does not remain. Therefore, in the third embodiment, the condensed water may remain in the steam outlet pipe 31 in the backup heat exchanger station but will not remain in the shell of the backup heat exchanger 24.
【００５３】[0053]
【発明の効果】本発明によれば、温水供給温度は外気温
度によらないである一定値、例えば60℃以上とし、空調
負荷への熱負荷の調整は各負荷ごとへの温水供給流量を
制御するか、蒸気トラップの設置位置を従来よりも約10
ｍ下方へ移設することによって行なう。According to the present invention, the hot water supply temperature is set to a constant value which does not depend on the outside air temperature, for example, 60 ° C. or higher, and the heat load to the air conditioning load is adjusted by controlling the hot water supply flow rate to each load. Or, install the steam trap at about 10
It will be done by moving it downward.
【００５４】この結果、バックアップ熱交換器の管側出
口温度が従来側に比較して高くなるため、バックアップ
熱交換器の胴内圧力を正圧に維持することができ、バッ
クアップ熱交換器の胴内への凝縮水の残留を回避でき
る。As a result, the outlet temperature on the tube side of the backup heat exchanger is higher than that on the conventional side, so that the internal pressure of the backup heat exchanger can be maintained at a positive pressure, and the backup heat exchanger can be maintained at a positive pressure. Condensed water can be prevented from remaining inside.
【図１】本発明に係る原子力発電所の所内温水系設備の
第１の実施例を示す系統図。FIG. 1 is a system diagram showing a first embodiment of an on-site hot water system facility of a nuclear power plant according to the present invention.
【図２】本発明に係る原子力発電所の所内温水系設備の
第２の実施例を示す系統図。FIG. 2 is a system diagram showing a second embodiment of a hot water system facility in a nuclear power plant according to the present invention.
【図３】本発明に係る原子力発電所の所内温水系設備の
第３の実施例を示す系統図。FIG. 3 is a system diagram showing a third embodiment of on-site hot water system equipment of a nuclear power plant according to the present invention.
【図４】従来の原子力発電所の所内温水系設備を示す系
統図。FIG. 4 is a system diagram showing a conventional hot water system facility of a nuclear power plant.
【図５】図４における温水供給温度と外気温度との関係
を示す特性図。5 is a characteristic diagram showing the relationship between the hot water supply temperature and the outside air temperature in FIG.
【図６】図４における所内温水系設備の定期検査時の状
態を示す系統図。FIG. 6 is a system diagram showing a state of a hot water system facility in the plant in FIG. 4 at the time of periodic inspection.
１…原子炉補機冷却系、２…冷却水供給配管、３…原子
炉冷却材浄化系非再生熱交換器、４…冷却水戻り配管、
５…温水熱交換器、６…温水熱交換器出口配管、７…バ
ックアップ熱交換器バイパス配管、８…温水供給配管、
９…空調負荷、10…所内温水戻り配管、11…所内温水ポ
ンプ、12…所内温水ポンプ出口配管、13…温水熱交換器
入口配管、14…外気温度、15…外気温度検出点、16…温
度調節器、17…温度供給温度検出点、18…温度調整弁
（高温側）、19…第２の温水熱交換器バイパス配管、20
…温度調整弁（低温側）、21…温水熱交換器入口弁、22
…バックアップ熱交換器バイパス弁、23…バックアップ
熱交換器入口弁、24…バックアップ熱交換器、25…所内
蒸気設備、26…第１の温水熱交換器バイパス配管、27…
バックアップ熱交換器入口配管、28…バックアップ熱交
換器出口配管、29…バックアップ熱交換器所内蒸気入口
配管、30…バックアップ熱交換器所内蒸気入口弁、31…
バックアップ熱交換器所内蒸気出口配管、32…蒸気トラ
ップ、33…蒸気トラップ出口配管、34…温度検出器、35
…温度調節器、36…温水供給流量調整弁、37…流量検出
器、38…流量調節器、39…所内温水バイパス配管、40…
所内温水バイパス流量調整弁、41…温度検出器、42…温
度調節器、43…フロア、44…階下フロア。1 ... Reactor auxiliary cooling system, 2 ... Cooling water supply pipe, 3 ... Reactor coolant purification system non-regenerative heat exchanger, 4 ... Cooling water return pipe,
5 ... hot water heat exchanger, 6 ... hot water heat exchanger outlet pipe, 7 ... backup heat exchanger bypass pipe, 8 ... hot water supply pipe,
9 ... Air-conditioning load, 10 ... Station hot water return piping, 11 ... Station hot water pump, 12 ... Station hot water pump outlet piping, 13 ... Hot water heat exchanger inlet piping, 14 ... Outside air temperature, 15 ... Outside air temperature detection point, 16 ... Temperature Controller, 17 ... Temperature supply temperature detection point, 18 ... Temperature control valve (high temperature side), 19 ... Second hot water heat exchanger bypass pipe, 20
… Temperature control valve (low temperature side), 21… Hot water heat exchanger inlet valve, 22
… Backup heat exchanger bypass valve, 23… Backup heat exchanger inlet valve, 24… Backup heat exchanger, 25… On-site steam facility, 26… First hot water heat exchanger bypass pipe, 27…
Backup heat exchanger inlet piping, 28 ... Backup heat exchanger outlet piping, 29 ... Backup heat exchanger station steam inlet piping, 30 ... Backup heat exchanger station steam inlet valve, 31 ...
Backup heat exchanger station steam outlet pipe, 32 ... Steam trap, 33 ... Steam trap outlet pipe, 34 ... Temperature detector, 35
… Temperature controller, 36… Hot water supply flow rate control valve, 37… Flow rate detector, 38… Flow rate controller, 39… In-house hot water bypass pipe, 40…
On-site hot water bypass flow control valve, 41 ... Temperature detector, 42 ... Temperature controller, 43 ... Floor, 44 ... Floor floor.
Claims (3)
経て原子炉冷却材浄化系非再生熱交換器に補機冷却水を
供給し、原子炉水と熱交換された原子炉補機冷却水を冷
却水戻り配管を経て温水熱交換器へ導き、この温水熱交
換器で高温となった所内温水を温水熱交換器出口配管か
らバックアップ熱交換器バイパス配管および温水供給配
管を経て空調負荷へ供給し、この空調負荷で熱交換され
た所内温水を所内温水戻り配管を経て所内温水ポンプに
より所内温水ポンプ出口配管を経て前記温水熱交換器へ
導く前記温水熱交換器から前記空調負荷への系統と、所
内蒸気設備からの所内蒸気をバックアップ熱交換器へ導
き、このバックアップ熱交換器で所内蒸気として熱交換
された所内温水をバックアップ熱交換器出口配管から前
記温水供給配管を経て前記空調負荷へ供給し、前記バッ
クアップ熱交換器へ前記所内温水出口ポンプ出口配管か
ら第１の温水熱交換器バイパス配管を経て温水を導く前
記バックアップ熱交換器から前記空調負荷への系統を備
えた原子力発電所の所内温水系設備において、前記空調
負荷と前記温水供給配管との間に温水供給流量調整弁を
設け、この温水供給流量調整弁と前記空調負荷とを温度
検出器および温度調節器で電気的に接続し、前記温水供
給配管と前記所内温水戻り配管との間にバイパス流量調
整弁を有する所内温度バイパス配管を接続し、前記所内
温水ポンプの吐出側に流量検出器および流量調節器を直
列接続し、この流量調節器と前記温水供給流量調整弁と
を電気的に接続してなることを特徴とする原子力発電所
の所内温水系設備。1. A reactor auxiliary machine in which heat is exchanged with the reactor water by supplying the auxiliary machine cooling water from the reactor auxiliary machine cooling system to a non-regenerative heat exchanger of a reactor coolant purification system through a cooling water supply pipe. Cooling water is led to the hot water heat exchanger via the cooling water return pipe, and the hot water inside the plant that has reached a high temperature in this hot water heat exchanger is exhausted from the hot water heat exchanger outlet pipe to the backup heat exchanger bypass pipe and hot water supply pipe to provide an air conditioning load. To the hot air heat exchanger from the hot water heat exchanger to the hot water heat exchanger through the hot water pump outlet piping of the hot water pump to the hot water inside The system and the in-house steam from the in-house steam facility are guided to a backup heat exchanger, and the in-house hot water that has undergone heat exchange as in-house steam in this backup heat exchanger is passed from the backup heat exchanger outlet pipe to the hot water supply pipe. To the air conditioning load, and to introduce hot water to the backup heat exchanger from the in-house hot water outlet pump outlet pipe through the first hot water heat exchanger bypass pipe to a system from the backup heat exchanger to the air conditioning load. In a hot water system facility of a nuclear power plant, a hot water supply flow rate adjusting valve is provided between the air conditioning load and the hot water supply pipe, and the hot water supply flow rate adjusting valve and the air conditioning load are connected to a temperature detector and a temperature controller. Is electrically connected to the hot water supply pipe and the hot water return pipe in the place, and a temperature bypass pipe having a bypass flow rate adjusting valve is connected, and a flow rate detector and a flow rate regulator are provided on the discharge side of the hot water pump in the place. Is connected in series, and the hot water supply flow control valve and the flow controller are electrically connected to each other.
経て原子炉冷却材浄化系非再生熱交換器に補機冷却水を
供給し、原子炉水と熱交換された原子炉補機冷却水を冷
却水戻り配管を経て温水熱交換器へ導き、この温水熱交
換器で高温となった所内温水を温水熱交換器出口配管か
らバックアップ熱交換器バイパス配管および温水供給配
管を経て空調負荷へ供給し、この空調負荷で熱交換され
た所内温水を所内温水戻り配管を経て所内温水ポンプに
より所内温水ポンプ出口配管を経て前記温水熱交換器へ
導く前記温水熱交換器から前記空調負荷への系統と、所
内蒸気設備からの所内蒸気をバックアップ熱交換器へ導
き、このバックアップ熱交換器で所内蒸気として熱交換
された所内温水をバックアップ熱交換器出口配管から前
記温水供給配管を経て前記空調負荷へ供給し、前記バッ
クアップ熱交換器へ前記所内温水出口ポンプ出口配管か
ら第１の温水熱交換器バイパス配管を経て温水を導く前
記バックアップ熱交換器から前記空調負荷への系統を備
えた原子力発電所の所内温水系設備において、前記バッ
クアップ熱交換器出口配管に温度検出器および温度調節
器を直列接続し、前記温度調節器と前記バックアップ熱
交換器所内蒸気入口弁とを電気的に接続してなることを
特徴とする原子力発電所の所内温水系設備。2. A reactor auxiliary machine in which heat is exchanged with the reactor water by supplying the auxiliary machine cooling water from the reactor auxiliary machine cooling system to a non-regenerative heat exchanger of the reactor coolant purification system through a cooling water supply pipe. Cooling water is led to the hot water heat exchanger via the cooling water return pipe, and the hot water inside the plant that has reached a high temperature in this hot water heat exchanger is exhausted from the hot water heat exchanger outlet pipe to the backup heat exchanger bypass pipe and hot water supply pipe to provide an air conditioning load. To the hot air heat exchanger from the hot water heat exchanger to the hot water heat exchanger through the hot water pump outlet piping of the hot water pump to the hot water inside The system and the in-house steam from the in-house steam facility are guided to a backup heat exchanger, and the in-house hot water that has undergone heat exchange as in-house steam in this backup heat exchanger is passed from the backup heat exchanger outlet pipe to the hot water supply pipe. To the air conditioning load, and to introduce hot water to the backup heat exchanger from the in-house hot water outlet pump outlet pipe through the first hot water heat exchanger bypass pipe to a system from the backup heat exchanger to the air conditioning load. In a hot water facility in a nuclear power plant, a temperature detector and a temperature controller are connected in series to the backup heat exchanger outlet pipe, and the temperature controller and the steam inlet valve in the backup heat exchanger are electrically connected. A hot water system facility inside a nuclear power plant characterized by being connected.
経て原子炉冷却材浄化系非再生熱交換器に補機冷却水を
供給し、原子炉水と熱交換された原子炉補機冷却水を冷
却水戻り配管を経て温水熱交換器へ導き、この温水熱交
換器で高温となった所内温水を温水熱交換器出口配管か
らバックアップ熱交換器バイパス配管および温水供給配
管を経て空調負荷へ供給し、この空調負荷で熱交換され
た所内温水を所内温水戻り配管を経て所内温水ポンプに
より所内温水ポンプ出口配管を経て前記温水熱交換器へ
導く前記温水熱交換器から前記空調負荷への系統と、所
内蒸気設備からの所内蒸気をバックアップ熱交換器へ導
き、このバックアップ熱交換器で所内蒸気として熱交換
された所内温水をバックアップ熱交換器出口配管から前
記温水供給配管を経て前記空調負荷へ供給し、前記バッ
クアップ熱交換器へ前記所内温水出口ポンプ出口配管か
ら第１の温水熱交換器バイパス配管を経て温水を導く前
記バックアップ熱交換器から前記空調負荷への系統を備
えた原子力発電所の所内温水系設備において、前記バッ
クアップ熱交換器にバックアップ熱交換器所内蒸気出口
配管を前記バックアップ熱交換器を設置した設置フロア
より階下フロアにまで延長して接続し、このバックアッ
プ熱交換器所内蒸気出口配管に蒸気トラップを接続し、
この蒸気トラップに蒸気トラップ出口配管を接続し、こ
の蒸気トラップ出口配管を前記階下フロアよりさらに下
方へ延長してなることを特徴とする原子力発電所の所内
温水系設備。3. A reactor auxiliary machine in which heat is exchanged with the reactor water by supplying the auxiliary machine cooling water from the reactor auxiliary machine cooling system to a non-regenerative heat exchanger for reactor coolant purification system through a cooling water supply pipe. Cooling water is led to the hot water heat exchanger via the cooling water return pipe, and the hot water inside the plant that has reached a high temperature in this hot water heat exchanger is exhausted from the hot water heat exchanger outlet pipe to the backup heat exchanger bypass pipe and hot water supply pipe to provide an air conditioning load. To the hot air heat exchanger from the hot water heat exchanger to the hot water heat exchanger through the hot water pump outlet piping of the hot water pump to the hot water inside The system and the in-house steam from the in-house steam facility are guided to a backup heat exchanger, and the in-house hot water that has undergone heat exchange as in-house steam in this backup heat exchanger is passed from the backup heat exchanger outlet pipe to the hot water supply pipe. To the air conditioning load, and to introduce hot water to the backup heat exchanger from the in-house hot water outlet pump outlet pipe through the first hot water heat exchanger bypass pipe to a system from the backup heat exchanger to the air conditioning load. In the hot water system facility of the nuclear power plant, the backup heat exchanger is connected to the backup heat exchanger by extending the steam outlet pipe in the station to the floor below the installation floor where the backup heat exchanger is installed. Connect a steam trap to the steam outlet pipe in the exchange,
A hot water system facility in a nuclear power plant, characterized in that a steam trap outlet pipe is connected to the steam trap, and the steam trap outlet pipe is extended further below the lower floor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP30489294A JP3340866B2 (en) | 1994-12-08 | 1994-12-08 | Hot water system facilities in nuclear power plants |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP30489294A JP3340866B2 (en) | 1994-12-08 | 1994-12-08 | Hot water system facilities in nuclear power plants |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH08160189A true JPH08160189A (en) | 1996-06-21 |
| JP3340866B2 JP3340866B2 (en) | 2002-11-05 |
Family
ID=17938544
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP30489294A Expired - Fee Related JP3340866B2 (en) | 1994-12-08 | 1994-12-08 | Hot water system facilities in nuclear power plants |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3340866B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111430049A (en) * | 2020-03-19 | 2020-07-17 | 福建福清核电有限公司 | A return circuit for solving nuclear power station equipment cooling water system low temperature problem in winter |
-
1994
- 1994-12-08 JP JP30489294A patent/JP3340866B2/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111430049A (en) * | 2020-03-19 | 2020-07-17 | 福建福清核电有限公司 | A return circuit for solving nuclear power station equipment cooling water system low temperature problem in winter |
Also Published As
| Publication number | Publication date |
|---|---|
| JP3340866B2 (en) | 2002-11-05 |
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