JPH0521197B2 - - Google Patents
Info
- Publication number
- JPH0521197B2 JPH0521197B2 JP59020712A JP2071284A JPH0521197B2 JP H0521197 B2 JPH0521197 B2 JP H0521197B2 JP 59020712 A JP59020712 A JP 59020712A JP 2071284 A JP2071284 A JP 2071284A JP H0521197 B2 JPH0521197 B2 JP H0521197B2
- Authority
- JP
- Japan
- Prior art keywords
- hot water
- heat exchanger
- valve
- water
- water valve
- 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
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
- Steam Or Hot-Water Central Heating Systems (AREA)
- Breeding Of Plants And Reproduction By Means Of Culturing (AREA)
- Control Of Steam Boilers And Waste-Gas Boilers (AREA)
- Control Of Temperature (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
この発明は、原子炉建屋内の各所を暖房する原
子力発電所の暖房システムに関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a heating system for a nuclear power plant that heats various parts of a nuclear reactor building.
一般に、原子力発電所の暖房システムは、原子
炉建屋内の各暖房対象を暖房する所内温水系を有
し、この系は第1図に示すように閉ループを成し
ている。
In general, a heating system of a nuclear power plant has an in-station hot water system that heats each heating target in a nuclear reactor building, and this system forms a closed loop as shown in FIG. 1.
この所内温水系2には温水熱交換器3が配設さ
れ、この系2を流れる循環水は、この温水熱交換
器3を介して、原子炉冷却材浄化系5の非再熱交
換器7からの排熱により一定温度に加熱される。
この加熱された循環水は温水ポンプ9により、自
動温度調整弁11を介して暖房対象13に送ら
れ、暖房対象13が暖房される。 A hot water heat exchanger 3 is disposed in this station hot water system 2, and the circulating water flowing through this system 2 is passed through the hot water heat exchanger 3 to a non-reheat exchanger 7 of a reactor coolant purification system 5. It is heated to a constant temperature by the exhaust heat from.
This heated circulating water is sent to the heating object 13 by the hot water pump 9 via the automatic temperature control valve 11, and the heating object 13 is heated.
暖房対象13の温度は、自動温度調整弁11に
よりほぼ所定値に制御される。つまり、温度検出
器15により検出される暖房対象13の温度に応
じて、自動温度調整弁11の弁開度を調整し、一
定温度に加熱された循環水の流量を変化させる。
外気温度が低く暖房対象13の温度が所定値より
低い場合には、調整弁11の開度を大としてこの
暖房対象へ送る循環水流量を増加させる。また、
暖房対象13が所定値より高温であるときは、弁
11の開度を小としこの暖房対象へ送る循環水流
量を減少させる。 The temperature of the heating object 13 is controlled to approximately a predetermined value by the automatic temperature control valve 11. That is, the valve opening degree of the automatic temperature adjustment valve 11 is adjusted according to the temperature of the heating object 13 detected by the temperature detector 15, and the flow rate of circulating water heated to a constant temperature is changed.
When the outside air temperature is low and the temperature of the heating object 13 is lower than a predetermined value, the opening degree of the regulating valve 11 is increased to increase the flow rate of circulating water sent to the heating object. Also,
When the temperature of the heating object 13 is higher than a predetermined value, the opening degree of the valve 11 is reduced to reduce the flow rate of circulating water sent to the heating object.
ところが、第2図に示すように、日本のある地
方における気温の通年変化によれば、最低気温が
0℃以下となつて自動温度調整弁11を全開状態
とさせねばならない厳寒期は非常に短かく、他の
期間は弁11を締り、特に温暖な期間には弁11
を締切状態に近い開度にしている。自動温度調整
弁11のこのような開度変化に伴い温水ポンプ9
はその運転流量範囲が広くなり、負荷が大幅に変
動する。その結果、温水ポンプ9の運転が不安定
となり、暖房システム1の信頼性が低下するおそ
れがある。特に、自動温度調整弁11が締切状態
に近い開度の場合には、ポンプ羽根車がケーシン
グポンプ内の温水を掻き回し、温水ポンプ9が過
熱する危険もある。 However, as shown in Figure 2, according to year-round changes in temperature in certain regions of Japan, the severe cold period when the minimum temperature drops below 0°C and the automatic temperature control valve 11 must be fully opened is very short. Thus, during other periods, valve 11 is closed, and during particularly warm periods, valve 11 is closed.
The opening is close to the closing state. Due to such a change in the opening degree of the automatic temperature control valve 11, the hot water pump 9
The operating flow range becomes wider and the load fluctuates significantly. As a result, the operation of the hot water pump 9 may become unstable, and the reliability of the heating system 1 may decrease. In particular, when the automatic temperature control valve 11 is at an opening close to the closed state, there is a risk that the pump impeller stirs the hot water in the casing pump, causing the hot water pump 9 to overheat.
また、温水ポンプ9の運転流量範囲が広いため
ポンプ設計に特別な配慮が必要となり、さらにポ
ンプ運転状態の監視も困難になる。 Furthermore, since the operating flow rate range of the hot water pump 9 is wide, special consideration is required in pump design, and furthermore, it becomes difficult to monitor the pump operating state.
また、自動温度調整弁11は自動操作機構を有
するため、手動弁に較べて故障が多く暖房システ
ムの信頼性が低下する。さらに、自動温度調整弁
11は各暖房対象13の入口部分にそれぞれ設け
られるので、保守点検作業に長時間を要し、しか
もコストの上昇が避けられない。 In addition, since the automatic temperature control valve 11 has an automatic operation mechanism, it is more likely to fail than a manual valve, reducing the reliability of the heating system. Furthermore, since the automatic temperature control valve 11 is provided at the inlet of each heating object 13, maintenance and inspection work takes a long time, and an increase in cost is unavoidable.
この発明は、上記事実に鑑みなされたもので、
システムの信頼性を向上させ、保守点検を容易に
し、さらにコストの低減を図ることができる原子
力発電所の暖房システムを提供することを目的と
する。
This invention was made in view of the above facts,
The purpose of the present invention is to provide a heating system for a nuclear power plant that can improve system reliability, facilitate maintenance and inspection, and further reduce costs.
上記目的を達成するために、特許請求の範囲第
1項記載の発明に係る原子力発電所の暖房システ
ムは、原子炉建屋内の暖房対象を暖房する閉ルー
プの所内温水系を有する原子力発電所の暖房シス
テムにおいて、上記所内温水系に配設され、原子
炉冷却材浄化系の非再生熱交換器からの熱量を受
熱して上記所内温水系の循環水を加熱する温水熱
交換器と、上記所内温水系に配設され、上記加熱
された循環水を循環させる温水ポンプと、上記所
内温水系の上記温水ポンプ上流側に配設されて冷
水弁、温水弁および制御演算部を備えた温度調整
装置と、を有し、上記温水弁は、上記温水熱交換
器の下流側に接続され、上記循環水のうちこの温
水熱交換器で加熱された温水を導びき、上記冷水
弁は、上記温水熱交換器を迂回するバイパス配管
に配設されて、上記循環水のうちこのバイパス配
管を流れる冷水を導びき、上記制御演算部は、外
気温度検出器並びに上記温水弁および冷水弁に接
続され、上記外気温度検出器からの信号に基づき
上記両弁の開度を調整して、上記冷水弁からの冷
水流量と上記温水弁からの温水流量とを変化さ
せ、これら冷水および温水が混合された混合水の
流量を一定に維持しつつ、その混合水の温度を外
気温度に追従して制御させたものである。
In order to achieve the above object, a heating system for a nuclear power plant according to the invention described in claim 1 provides a heating system for a nuclear power plant that has a closed-loop in-house hot water system that heats objects to be heated in a nuclear reactor building. The system includes a hot water heat exchanger that is disposed in the station hot water system and heats the circulating water of the station hot water system by receiving heat from the non-regenerative heat exchanger of the reactor coolant purification system; a hot water pump disposed in a system to circulate the heated circulating water; and a temperature adjustment device disposed upstream of the hot water pump in the in-house hot water system and including a cold water valve, a hot water valve, and a control calculation unit. , the hot water valve is connected to the downstream side of the hot water heat exchanger and guides hot water heated by the hot water heat exchanger out of the circulating water, and the cold water valve is connected to the hot water heat exchanger. The control calculation unit is connected to an outside air temperature detector and the hot water valve and cold water valve, and is connected to the outside air temperature detector and the hot water valve and the cold water valve, and is connected to the outside air temperature detector and the hot water valve and the cold water valve, and is connected to the outside air temperature detector and the hot water valve and the cold water valve, Based on the signal from the temperature sensor, the opening degrees of both valves are adjusted to change the flow rate of cold water from the cold water valve and the flow rate of hot water from the hot water valve, and the mixed water, which is a mixture of cold water and hot water, is The temperature of the mixed water is controlled to follow the outside air temperature while keeping the flow rate constant.
また、特許請求の範囲第3項記載の発明は、原
子炉建屋内の暖房対象を暖房する閉ループの所内
温水系を有する原子力発電所の暖房システムにお
いて、常時一定量の循環水が流れる上記所内温水
系に配設され、原子炉冷却材浄化系の非再生熱交
換器からの熱量を受熱して上記所内温水系の循環
水を加熱する温水熱交換器と、上記所内温水系に
配設され、上記加熱された循環水を循環させる温
水ポンプと、非再生熱交換器からの排熱を上記温
水熱交換器へ輸送する原子炉補機冷却系に配設さ
れて冷水弁、温水弁および制御演算部を備えた温
度調整装置とを有し、上記冷水弁は、上記温水熱
交換器の下流側に接続され、上記非再生熱交換器
から上記温水熱交換器へ導かれて低温化された冷
却水を冷水として導びき、上記温水弁は、上記温
水熱交換器を迂回するバイパス配管に接続されて
上記非再生熱交換器から高温の冷却水を温水とし
て導びき、上記制御演算部は、外気温度検出器並
びに上記冷水弁および温水弁に接続され、上記外
気温度検出器からの信号に基づき上記両弁の開度
を調整して上記冷水流量を変化させることによ
り、外気温度に追従して上記循環水温度を制御す
るものである。これら両発明ともに、温水ポンプ
の負荷変動幅を小としポンプ運転性能を向上させ
るものである。 Further, the invention described in claim 3 provides a heating system for a nuclear power plant having a closed-loop in-house hot water system that heats objects to be heated in a nuclear reactor building, in which a certain amount of circulating water always flows. a hot water heat exchanger disposed in the reactor coolant purification system that receives heat from a non-regenerative heat exchanger of the reactor coolant purification system to heat circulating water of the station hot water system, and a hot water heat exchanger disposed in the station hot water system; A hot water pump that circulates the heated circulating water, a reactor auxiliary cooling system that transports waste heat from the non-regenerative heat exchanger to the hot water heat exchanger, and a cold water valve, a hot water valve, and control calculations. the cold water valve is connected to the downstream side of the hot water heat exchanger, and the cold water valve is connected to the downstream side of the hot water heat exchanger, and the cold water valve is connected to the hot water heat exchanger to cool the cooled water that has been guided from the non-regenerative heat exchanger to the hot water heat exchanger. The hot water valve is connected to a bypass pipe that bypasses the hot water heat exchanger to lead high temperature cooling water from the non-regenerative heat exchanger as hot water, and the control calculation unit It is connected to a temperature sensor, the cold water valve, and the hot water valve, and adjusts the opening degree of both valves based on the signal from the outside air temperature sensor to change the cold water flow rate, thereby following the outside air temperature. It controls the temperature of circulating water. Both of these inventions are intended to reduce the load fluctuation range of the hot water pump and improve pump operating performance.
以下、この発明の実施例を図面に基づいて説明
する。
Embodiments of the present invention will be described below based on the drawings.
第3図はこの発明に係る原子力発電所の暖房シ
ステムの第一実施例を示す系統図である。 FIG. 3 is a system diagram showing a first embodiment of a heating system for a nuclear power plant according to the present invention.
原子力発電所の暖房システム20は、所内温水
系21、原子炉冷却材浄化系23および原子炉補
機冷却系25から構成される。このうち所内温水
系21は、原子炉冷却材浄化系23から排出され
る熱量を原子炉補機冷却系25を介して受熱し、
原子炉建屋内の各暖房対象26を所定の温度に暖
房する系統である。また、原子炉冷却材浄化系2
3は、原子炉圧力容器27内で生成する不純物を
取り除く系統である。 A heating system 20 of a nuclear power plant includes an in-station hot water system 21, a reactor coolant purification system 23, and a reactor auxiliary equipment cooling system 25. Of these, the station hot water system 21 receives the amount of heat discharged from the reactor coolant purification system 23 via the reactor auxiliary equipment cooling system 25,
This is a system that heats each heating object 26 in the reactor building to a predetermined temperature. In addition, reactor coolant purification system 2
3 is a system for removing impurities generated within the reactor pressure vessel 27.
原子炉冷却材浄化系23では、原子炉圧力容器
27に循環ポンプ29、再生熱交換器31、非再
生熱交換器33および浄化装置35が順次配設さ
れる。非再生熱交換器33により、冷却材は浄化
のための最適な温度まで冷却される。また、冷却
水が浄化装置35を通過することにより、炉心で
発生した核分裂生成物、原子炉圧力容器27内の
腐食生成物が除去される。浄化装置35の出口側
は再生熱交換器31を介して原子炉圧力容器27
に連接される。したがつて浄化された冷却水は、
再生熱交換器31を通過することにより昇温され
て、原子炉圧力容器27に導かれる。 In the reactor coolant purification system 23, a circulation pump 29, a regenerative heat exchanger 31, a non-regenerative heat exchanger 33, and a purification device 35 are sequentially arranged in the reactor pressure vessel 27. The non-regenerative heat exchanger 33 cools the coolant to the optimum temperature for purification. Further, as the cooling water passes through the purification device 35, fission products generated in the reactor core and corrosion products in the reactor pressure vessel 27 are removed. The outlet side of the purification device 35 is connected to the reactor pressure vessel 27 via the regenerative heat exchanger 31.
connected to. Therefore, the purified cooling water is
The temperature is raised by passing through the regenerative heat exchanger 31 and then introduced into the reactor pressure vessel 27.
一方、原子炉補機冷却系25は、非再生熱交換
器33と所内温水系21の温水熱交換器37とを
連接する閉ループであり、このループに冷却水ポ
ンプ39が設けられる。原子炉補機冷却系25内
の冷却水は、冷却水ポンプ39によりこの系25
を循環し、非再生熱交換器33からの排熱を温水
熱交換器37に輸送する。 On the other hand, the reactor auxiliary cooling system 25 is a closed loop that connects the non-regenerative heat exchanger 33 and the hot water heat exchanger 37 of the station hot water system 21, and a cooling water pump 39 is provided in this loop. Cooling water in the reactor auxiliary cooling system 25 is pumped to this system 25 by a cooling water pump 39.
The exhaust heat from the non-regenerative heat exchanger 33 is transported to the hot water heat exchanger 37.
また、所内温水系21は一つまたは複数の暖房
対象26を一つの温水加熱器37に並列に連接す
るものであり、閉ループから構成される。このル
ープには温水ポンプ41が配設され、これにより
温水熱交換器37および各暖房対象26間を循環
水が循環する。各暖房対象26の入口側には、流
量調整弁としての入口弁43がそれぞれ設けられ
る。この入口弁43は、各暖房対象26へ供給さ
れる循環水の流量をバランスさせ、あるいは保
守・点検のために暖房対象26を所内温水系21
から離隔させる機能を有する。なお、この入口弁
43は手動弁が用いられるが、特に精密な温度制
御が要求される暖房対象26には、従来例で使用
されたと同様な自動温度調整弁が設けられる。 Further, the in-house hot water system 21 connects one or more heating objects 26 to one hot water heater 37 in parallel, and is configured as a closed loop. A hot water pump 41 is disposed in this loop, thereby circulating water between the hot water heat exchanger 37 and each heating object 26. An inlet valve 43 serving as a flow rate regulating valve is provided on the inlet side of each heating target 26. This inlet valve 43 is used to balance the flow rate of circulating water supplied to each heating target 26, or to transfer the heating target 26 to the in-house hot water system 21 for maintenance and inspection.
It has the function of separating from the Although a manual valve is used as the inlet valve 43, the heating object 26, which requires particularly precise temperature control, is provided with an automatic temperature control valve similar to that used in the conventional example.
また、所内温水系21には、温水熱交換器37
を迂回するバイパス配管45が設けられる。この
バイパス管45は、暖房対象26の下流側と温水
ポンプ41の吸入側とを直接連結するものであ
り、この温水ポンプ41の吸入側連結部に温度調
整装置47が配設される。さらに、バイパス配管
45には流量制限オリフイス49が設けられる。
この流量制限オリフイス49は、バイパス配管4
5を流れる循環水に、温水熱交換器37を流れる
と同等の圧力損失を与えるものである。その結
果、温度調整装置47において、流量制限オリフ
イス49および温水熱交換器37からそれぞれ流
出する循環水の混合が容易化される。 In addition, the in-house hot water system 21 includes a hot water heat exchanger 37.
Bypass piping 45 is provided to bypass the. This bypass pipe 45 directly connects the downstream side of the heating object 26 and the suction side of the hot water pump 41, and a temperature adjustment device 47 is disposed at the suction side connection portion of the hot water pump 41. Further, the bypass pipe 45 is provided with a flow rate limiting orifice 49 .
This flow rate limiting orifice 49 is connected to the bypass piping 4.
This gives the same pressure loss to the circulating water flowing through the hot water heat exchanger 37. As a result, in the temperature adjustment device 47, mixing of the circulating water flowing out from the flow rate limiting orifice 49 and the hot water heat exchanger 37 is facilitated.
温度調整装置47は冷水弁51および温水弁5
3と、これら冷水弁51および温水弁53に電気
的に接続される制御演算器55とを有して構成さ
れる。冷水弁51は流量制限オリフイス49の、
また温水弁53は温水熱交換器37のそれぞれ出
口側に接続される。さらに、冷水弁51および温
水弁53の流出側は合流して温水ポンプ41に連
結される。したがつて、この冷水弁51および温
水弁53が、温水熱交換器37で加熱された循環
水(温水)とバイパス配管45を流れる低温の循
環水(冷水)とを混合し、この混合水を温水ポン
プ41に導びく。 The temperature adjustment device 47 includes a cold water valve 51 and a hot water valve 5.
3, and a control calculator 55 electrically connected to the cold water valve 51 and the hot water valve 53. The cold water valve 51 is connected to the flow restriction orifice 49.
Further, the hot water valves 53 are connected to respective outlet sides of the hot water heat exchanger 37. Furthermore, the outflow sides of the cold water valve 51 and the hot water valve 53 merge and are connected to the hot water pump 41. Therefore, the cold water valve 51 and the hot water valve 53 mix the circulating water (hot water) heated by the hot water heat exchanger 37 and the low-temperature circulating water (cold water) flowing through the bypass piping 45, and the mixed water is It leads to hot water pump 41.
また、制御演算器55には外気温度検出器57
が電気的に接続されるとともに、暖房対象26を
所定温度に保つために必要な循環水温度と外気温
度との関係式(第4図)が記憶される。外気温度
検出器57からの検出値および上記関係式に基づ
いて、制御演算器55が冷水弁51および温水弁
53のそれぞれの開度を調整することにより、混
合水の流量を一定としつつ温水および冷水の混合
比を変化させ、混合水の温度を所望の温度に制御
する。 The control calculator 55 also includes an outside air temperature detector 57.
are electrically connected, and a relational expression (FIG. 4) between the circulating water temperature and the outside air temperature necessary to maintain the heating object 26 at a predetermined temperature is stored. Based on the detected value from the outside air temperature detector 57 and the above relational expression, the control calculator 55 adjusts the respective opening degrees of the cold water valve 51 and the hot water valve 53, thereby maintaining the flow rate of the mixed water constant while maintaining the hot water and the hot water. The temperature of the mixed water is controlled to a desired temperature by changing the mixing ratio of cold water.
次に、作用を説明する。 Next, the effect will be explained.
原子炉冷却材浄化系21および原子炉補機冷却
系23が作動すると、非再生熱交換器33の排熱
が炉内温水系21の温水熱交換器37に輸送され
る。 When the reactor coolant purification system 21 and the reactor auxiliary cooling system 23 operate, the exhaust heat of the non-regenerative heat exchanger 33 is transported to the hot water heat exchanger 37 of the in-core hot water system 21 .
次に、所内温水系21を作動させる。温水ポン
プ41が駆動すると循環水は入口弁43を介して
各暖房対象26に導かれ、これらの暖房対象26
を暖房する。この暖房後循環水は低温化し冷水と
なつて、バイパス配管45および温水熱交換器3
7に導かれる。温水熱交換器37に導かれた循環
水は、非再生熱交換器33の排熱を受熱して高温
化し温水となり、温水弁53に導かれる。一方、
バイパス配管45に導かれた循環水は、流量制限
オリフイス49を経て冷水弁51に導かれる。 Next, the in-house hot water system 21 is activated. When the hot water pump 41 is driven, the circulating water is guided to each heating object 26 via the inlet valve 43,
heating. After heating, the circulating water is cooled and becomes cold water, and is transferred to the bypass pipe 45 and the hot water heat exchanger 3.
Guided by 7. The circulating water guided to the hot water heat exchanger 37 receives exhaust heat from the non-regenerative heat exchanger 33 and becomes hot water, and is guided to the hot water valve 53. on the other hand,
The circulating water guided to the bypass pipe 45 is guided to the cold water valve 51 via a flow rate limiting orifice 49.
また、外気温度検出器57で検出された外気温
度が制御演算器55に入力されると、制御演算器
55は、温水弁53および冷水弁51の開度を調
整制御する。この調整制御は、温水ポンプ41に
導かれる循環水(混合水)が一定の流量を維持
し、かつこの循環水温度が第4図の関係式から外
気温度に対応する値となるように行なわれる。例
えば、第4図によれば、外気温度が低いときほど
多量の熱量を供給しなければならないため、混合
水の流量一定の条件の下で、温水弁53の開度を
大とし、冷水弁51を絞る。 Further, when the outside air temperature detected by the outside air temperature detector 57 is input to the control calculator 55, the control calculator 55 adjusts and controls the opening degrees of the hot water valve 53 and the cold water valve 51. This adjustment control is performed so that the circulating water (mixed water) guided to the hot water pump 41 maintains a constant flow rate, and the temperature of the circulating water becomes a value corresponding to the outside air temperature according to the relational expression shown in FIG. . For example, according to FIG. 4, as the outside temperature is lower, a larger amount of heat must be supplied, so under the condition that the flow rate of the mixed water is constant, the opening degree of the hot water valve 53 is increased, and the opening degree of the cold water valve 51 is increased. Narrow down.
その結果、温水弁53および冷水弁51から流
出し混合して温水ポンプ41に導かれる循環水
(混合水)は、所定の温度かつ一定の流量に維持
される。この循環水が温水ポンプ41を経て暖房
対象26へ供給されることにより、暖房対象26
は、外気温度の変化にかかわらず最適な温度に暖
房される。 As a result, the circulating water (mixed water) that flows out from the hot water valve 53 and the cold water valve 51, mixes, and is guided to the hot water pump 41 is maintained at a predetermined temperature and a constant flow rate. By supplying this circulating water to the heating object 26 via the hot water pump 41, the heating object 26
is heated to the optimum temperature regardless of changes in outside temperature.
上記実施例によれば、所内温水系21を流れる
循環水の流量を一定に設定していることから、温
水ポンプ31の運転性能が安定化し、暖房システ
ムの信頼性を向上させることができる。特に、流
量が少ないことから生ずる温水ポンプ31の過熱
現象を回避することができるため、ポンプ運転状
態を監視するる必要がなく、暖房システムの保守
点検を簡素化することができる。また、循環水が
一定流量であるため、温水ポンプ31の負荷変動
範囲が小さく、ポンプはこの狭い負荷範囲で所定
の性能を発揮すればよい。したがつて、温水ポン
プ31の設計が容易となり、コストの低減を図る
ことができる。 According to the above embodiment, since the flow rate of the circulating water flowing through the in-house hot water system 21 is set constant, the operational performance of the hot water pump 31 is stabilized, and the reliability of the heating system can be improved. In particular, it is possible to avoid overheating of the hot water pump 31 caused by a low flow rate, so there is no need to monitor the pump operating state, and maintenance and inspection of the heating system can be simplified. Furthermore, since the circulating water has a constant flow rate, the load fluctuation range of the hot water pump 31 is small, and the pump only needs to exhibit a predetermined performance within this narrow load range. Therefore, the hot water pump 31 can be easily designed and costs can be reduced.
また、入口弁43が手動弁である場合には、自
動温度調整弁に較べ故障が少なく安価であるた
め、暖房システムの信頼性向上およびコストの低
減を図ることができる。さらに、弁を自動制御す
るための付属機器が不要となるため、システムの
保守点検を容易にすることができる。 Further, when the inlet valve 43 is a manual valve, it is less likely to fail and is less expensive than an automatic temperature control valve, so it is possible to improve the reliability of the heating system and reduce costs. Furthermore, since there is no need for accessory equipment for automatically controlling the valve, maintenance and inspection of the system can be facilitated.
第5図は、この発明に係る原子炉発電所の暖房
システムの第二実施例を示す系統図である。この
実施例において、第一実施例と同様な部分は同一
の符号を附すことにより説明を省略する。 FIG. 5 is a system diagram showing a second embodiment of the heating system for a nuclear power plant according to the present invention. In this embodiment, parts similar to those in the first embodiment are designated by the same reference numerals, and a description thereof will be omitted.
この暖房システム60では、所内温水系61に
二基の温水熱交換器が直列に配設される。これら
第一および第二温水熱交換器63,65の容量は
第一実施例の温水熱交換器37の容量より若干小
に設計される。このうち、第一温水熱交換器63
は第一流量制限オリフイス67と、また第二温水
熱交換器65は第二流量制限オリフイス69とそ
れぞれ並列に配設される。第一および第二温水熱
交換器63,65の接続部と第一および第二流量
制御オリフイスの接続部とは、バイパス弁71を
介して接続される。また、第一温水熱交換器63
の入口側でバイパス管45の分岐点72の下流側
配管には切換弁73が設けられる。これらのバイ
パス弁71および切換弁73は制御演算器55に
電気的に接続され、この制御演算器55により開
閉制御される。 In this heating system 60, two hot water heat exchangers are arranged in series in an in-house hot water system 61. The capacities of these first and second hot water heat exchangers 63, 65 are designed to be slightly smaller than the capacity of the hot water heat exchanger 37 of the first embodiment. Of these, the first hot water heat exchanger 63
is arranged in parallel with the first flow rate limiting orifice 67, and the second hot water heat exchanger 65 is arranged in parallel with the second flow rate limiting orifice 69, respectively. The connecting portions of the first and second hot water heat exchangers 63 and 65 and the connecting portions of the first and second flow control orifices are connected via a bypass valve 71. In addition, the first hot water heat exchanger 63
A switching valve 73 is provided on the downstream side of the branch point 72 of the bypass pipe 45 on the inlet side of the bypass pipe 45 . The bypass valve 71 and the switching valve 73 are electrically connected to the control calculator 55, and are controlled to open and close by the control calculator 55.
次に、この実施例の作用を説明する。 Next, the operation of this embodiment will be explained.
外気温度が極めて低い場合には、外気温度検出
器57これを検知し、この検出値が制御演算器5
5に入力される。すると、制御演算器55は、バ
イパス弁71を閉としかつ切換弁73を開とする
信号を出力する。これにより、暖房対象26を通
過した循環水は分岐点72で分流し、このうちの
一方は、切換弁73を経て第一および第二温水熱
交換器63,65に順次導かれる。循環水はこの
第一および第二温水熱交換器63,65で加熱さ
れ、温水となつて温水弁53に至る。また、合流
した循環水の他方は、第一および第二流量制限オ
リフイス67,69を通過し、低温状態の冷水の
まま冷水弁51に導かれる。 When the outside air temperature is extremely low, the outside air temperature detector 57 detects this, and this detected value is sent to the control calculator 5.
5 is input. Then, the control calculator 55 outputs a signal that closes the bypass valve 71 and opens the switching valve 73. As a result, the circulating water that has passed through the heating target 26 is divided at the branch point 72, and one of the water is sequentially guided to the first and second hot water heat exchangers 63 and 65 via the switching valve 73. The circulating water is heated by the first and second hot water heat exchangers 63 and 65, becomes hot water, and reaches the hot water valve 53. The other part of the combined circulating water passes through the first and second flow rate limiting orifices 67 and 69 and is guided to the cold water valve 51 as cold water at a low temperature.
制御演算器55は、二基の熱交換器で加熱され
た温水の温度を考慮し、温水と冷水との混合水が
第4図の関係式を満足するよう両弁51,53の
開度を設定する。この設定の際には、混合水の流
量が一定量を維持するよう勘案される。その後、
所望の温度に調整された混合水としての循環水が
温水ポンプ41を経て各暖房対象26に供給さ
れ。 The control calculator 55 takes into account the temperature of the hot water heated by the two heat exchangers and adjusts the opening degrees of both valves 51 and 53 so that the mixed water of hot water and cold water satisfies the relational expression shown in FIG. Set. When making this setting, consideration is given to maintaining a constant flow rate of the mixed water. after that,
Circulating water as mixed water adjusted to a desired temperature is supplied to each heating target 26 via the hot water pump 41.
また、外気温度が中程度に低い場合には、制御
演算器55からの信号により、切換弁73が閉
じ、バイパス弁71が開く。これにより、暖房対
象26を通過した循環水は第一流量制限オリフイ
ス67を経た後、バイパス弁71を通過するもの
と、第二流量制限オリフイス69を通過するもの
とに分流する。バイパス弁71を通過した分流循
環水は第二温水熱交換器65で加熱されて温水弁
53に至る。また、第二流量制限オリフイス69
を通過した分流循環水は低温状態の冷水のまま冷
水弁51に導かれる。これらの温水弁53および
冷水弁51に導かれれた循環水(温水、冷水)
は、制御演算器55により第一実施例と同様にし
て混合され、温水ポンプ41を介して各暖房対象
26に供給される。 Further, when the outside air temperature is moderately low, the switching valve 73 is closed and the bypass valve 71 is opened in response to a signal from the control calculator 55. As a result, the circulating water that has passed through the heating target 26 passes through the first flow rate limiting orifice 67 and is then divided into water that passes through the bypass valve 71 and water that passes through the second flow rate limiting orifice 69. The divided circulating water that has passed through the bypass valve 71 is heated by the second hot water heat exchanger 65 and reaches the hot water valve 53 . In addition, the second flow rate limiting orifice 69
The branched circulating water that has passed through is guided to the cold water valve 51 as cold water at a low temperature. Circulating water (hot water, cold water) led to these hot water valves 53 and cold water valves 51
are mixed by the control calculator 55 in the same manner as in the first embodiment, and supplied to each heating target 26 via the hot water pump 41.
第一実施例では、外気温度の極めて低い厳寒期
には温水弁53の開度を大とし、冷水弁51を著
しく絞つて運転する。ところが、冷水弁51が著
しく絞られると、弁の狭められた流路を冷水が高
速で流れ、キヤビテーシヨンやエロージヨンが発
生して冷水弁51を破損する恐れがある。外気温
度が高く温水弁53を大きく絞る場合にも、温水
弁53に同様の現象が生ずる恐れがある。 In the first embodiment, during the severe cold season when the outside air temperature is extremely low, the opening degree of the hot water valve 53 is increased and the cold water valve 51 is significantly throttled. However, if the cold water valve 51 is significantly constricted, the cold water will flow at high speed through the narrowed flow path of the valve, causing cavitation or erosion, which may damage the cold water valve 51. A similar phenomenon may occur in the hot water valve 53 when the outside air temperature is high and the hot water valve 53 is greatly throttled.
これに対し、この第二実施例では、循環水が温
水熱交換器の一基を通過するか、または二基を通
過するかにより、温水弁53に至る温水の温度を
粗調整することができる。例えば、外気温度高く
温水弁53の開度を小とす場合には、切換弁73
およびバイパス弁71を制御して第二温水熱交換
器65のみによ循環水を加温する。したがつて、
二基の温水熱交換器による場合に比べ温水弁53
に導かれる温水温度を低く調整することができ
る。その結果、所望の混合水温度を得るに際し、
第一実施例の場合に較べ、冷水量に対する温水量
の割合を大とすることができ、温水弁51を著し
く絞る必要がない。また、外気温度が極めて低く
冷水弁51を絞る場合にも、循環水を二基の温水
熱交換器で加温することにより、温水弁53に至
る温水(循環水)温度を第一実施例の場合に較べ
上昇させることができる。したがつて、この場合
にも冷水弁51を著しく絞る必要がない。 In contrast, in this second embodiment, the temperature of the hot water reaching the hot water valve 53 can be roughly adjusted depending on whether the circulating water passes through one hot water heat exchanger or two hot water heat exchangers. . For example, when the outside temperature is high and the opening degree of the hot water valve 53 is to be small, the switching valve 73
By controlling the bypass valve 71, the circulating water is heated only by the second hot water heat exchanger 65. Therefore,
Hot water valve 53 compared to the case with two hot water heat exchangers
The temperature of the hot water introduced can be adjusted to a lower value. As a result, when obtaining the desired mixed water temperature,
Compared to the case of the first embodiment, the ratio of the amount of hot water to the amount of cold water can be increased, and there is no need to significantly throttle the hot water valve 51. Furthermore, even when the outside air temperature is extremely low and the cold water valve 51 is throttled, by heating the circulating water with two hot water heat exchangers, the temperature of the hot water (circulating water) reaching the hot water valve 53 can be adjusted as in the first embodiment. This can be increased compared to the case. Therefore, in this case as well, there is no need to significantly throttle the cold water valve 51.
このように、温水弁53および冷水弁51を著
しく絞ることなく循環水温度を調整できるため、
この暖房システム60では前記第一実施例の効果
に加え、キヤビテーシヨンやエロージヨンにより
生ずる温水ポンプ41の破損を低減することがで
きる。 In this way, the circulating water temperature can be adjusted without significantly throttling the hot water valve 53 and the cold water valve 51.
In addition to the effects of the first embodiment, this heating system 60 can reduce damage to the hot water pump 41 caused by cavitation or erosion.
なお、上記第二実施例では、温水熱交換器を二
基直列するものにつき説明したが、三基またはそ
れ以上の温水熱交換器を配設するものであつても
よい。 In the second embodiment, two hot water heat exchangers are arranged in series, but three or more hot water heat exchangers may be arranged.
第6図は、この発明に係る原子力発電所の暖房
システムの第三実施例を示す系統図である。この
実施例において、第一実施例と同様な部分は同一
の符号を附すことにより説明を省略する。 FIG. 6 is a system diagram showing a third embodiment of a heating system for a nuclear power plant according to the present invention. In this embodiment, parts similar to those in the first embodiment are designated by the same reference numerals, and a description thereof will be omitted.
この暖房システム80では、所内温水系81
は、従来例(第1図)の温度検出器15がない点
および自動温度調整弁11の代わりに入口弁43
が設けられている点を除けば、従来例と同様な構
成であるが、補機冷却系83が異なる。つまり、
補機冷却系83には、温水熱交換器37を迂回し
てこの温水熱交換器37の上流側の冷却水をその
下流側に導くバイパス配管85が設けられる。こ
のバイパス配管85には流量制限オリフイス49
が配設され、また、バイパス配管85の下流側接
続部分に温度調整装置87が設けられる。 In this heating system 80, an in-house hot water system 81
The difference is that the temperature sensor 15 of the conventional example (FIG. 1) is not present, and the inlet valve 43 is used instead of the automatic temperature adjustment valve 11.
The configuration is similar to that of the conventional example except that the auxiliary cooling system 83 is different. In other words,
The auxiliary cooling system 83 is provided with a bypass pipe 85 that bypasses the hot water heat exchanger 37 and guides the cooling water upstream of the hot water heat exchanger 37 to its downstream side. This bypass piping 85 has a flow rate limiting orifice 49.
is provided, and a temperature adjustment device 87 is provided at the downstream connection portion of the bypass pipe 85.
この温度調整装置87は、第一実施例の温度調
整装置47と同様に冷水弁51、温水弁53、制
御演算器55および外気温度検出器57を有す
る。このうち冷水弁51は温水熱交換器37の下
流側配管に、温水弁53はバイパス配管85で流
量制限オリフイス49の下流側にそれぞれ設けら
れる。したがつて、冷水弁51には、原子炉冷却
材浄化系23の非再生熱交換器33により加熱さ
れ、温水熱交換器37に熱を輸送して低温化され
た冷却水(冷水)が導かれる。また、温水弁53
には、非再生熱交換器33で加熱された高温の冷
却水(温水)が流量制限オリフイス49を介して
導かれる。さらに、冷水弁51からの冷水および
温水弁53からの温水は合流され、図示しない熱
交換器を介して冷却水ポンプ39に導かれる。 This temperature adjustment device 87 has a cold water valve 51, a hot water valve 53, a control calculator 55, and an outside air temperature detector 57 similarly to the temperature adjustment device 47 of the first embodiment. Of these, the cold water valve 51 is provided in the downstream piping of the hot water heat exchanger 37, and the hot water valve 53 is provided in the bypass piping 85 downstream of the flow rate limiting orifice 49, respectively. Therefore, cooling water (chilled water) heated by the non-regenerative heat exchanger 33 of the reactor coolant purification system 23 and lowered in temperature by transporting heat to the hot water heat exchanger 37 is introduced into the cold water valve 51. It will be destroyed. In addition, hot water valve 53
In this case, high-temperature cooling water (warm water) heated by the non-regenerative heat exchanger 33 is introduced through the flow-limiting orifice 49. Furthermore, the cold water from the cold water valve 51 and the hot water from the hot water valve 53 are combined and guided to the cooling water pump 39 via a heat exchanger (not shown).
この実施例においても、冷水弁51および温水
弁53は、制御演算器55により、第一実施例と
同様にその開度が制御される。この開度制御によ
り、温水熱交換器37に導かれる冷却水(冷水)
量が変化し、この変化に伴い、所内温水系81を
一定流量で流れる循環水の温度が所望の温度に調
整される。したがつて、この実施例の場合にも、
第一実施例と同様な効果を得ることができる。 Also in this embodiment, the opening degrees of the cold water valve 51 and the hot water valve 53 are controlled by the control calculator 55 in the same manner as in the first embodiment. Cooling water (cold water) guided to the hot water heat exchanger 37 by this opening degree control.
The amount changes, and in accordance with this change, the temperature of the circulating water flowing at a constant flow through the in-house hot water system 81 is adjusted to a desired temperature. Therefore, also in this example,
The same effects as in the first embodiment can be obtained.
第7図は、この発明に係る原子力発電所の暖房
システムの第四実施例の一部を示す系統図であ
る。この実施例においても、第二および第三実施
例と同様な部分は同一の符号を附すことにより説
明を省略する。 FIG. 7 is a system diagram showing a part of a fourth embodiment of a heating system for a nuclear power plant according to the present invention. In this embodiment as well, the same parts as in the second and third embodiments are given the same reference numerals, and the explanation thereof will be omitted.
この実施例は第三実施例に対し、第二実施が第
一実施例に対した構成と同様の構成を有する。つ
まり、暖房システム90の所内温水系91には第
一および第二温水熱交換器63,65直列に設け
られ、さらに、これらの温水熱交換器63,65
を迂回するバイパス配管85が設けられる。この
バイパス配管85には第一および第二流量制限オ
リフイス67,69が配設される。第一および第
二温水熱交換器63,65の接続部と第一および
第二流量制限オリフイス67,69の接続部と
は、バイパス弁71を介して接続される。また、
第二温水熱交換器65の上流近傍に切換弁73が
配設される。さらに、第1温水熱交換器63の下
流側配管とバイパス配管85の下流側との接続部
に温度調整装置87が設けられる。この温度調整
装置87の制御演算器55が、バイパス弁71お
よび切換弁73に電気的に接続される。 This embodiment has the same configuration as the third embodiment and the second embodiment has the same configuration as the first embodiment. In other words, the in-house hot water system 91 of the heating system 90 is provided with first and second hot water heat exchangers 63 and 65 in series, and these hot water heat exchangers 63 and 65 are also provided in series.
Bypass piping 85 is provided to bypass the. This bypass piping 85 is provided with first and second flow rate limiting orifices 67, 69. The connecting portions of the first and second hot water heat exchangers 63 and 65 and the connecting portions of the first and second flow rate limiting orifices 67 and 69 are connected via a bypass valve 71. Also,
A switching valve 73 is disposed near the upstream of the second hot water heat exchanger 65. Further, a temperature adjustment device 87 is provided at a connection between the downstream side piping of the first hot water heat exchanger 63 and the downstream side of the bypass piping 85. The control calculator 55 of the temperature adjustment device 87 is electrically connected to the bypass valve 71 and the switching valve 73.
したがつて、外気温度の変化に伴い、バイパス
弁71および切換弁73を開閉制御することによ
り、温水熱交換器を一基または二基選択的に作動
させ、これにより所内温水系91の循環水温度を
粗調整する。つぎに、冷水弁51および温水弁5
3の開度を調整して、循環水温度を外気温度に適
合する所望の温度に設定する。このように、バイ
パス弁71および切換弁73の制御により循環水
温度を粗調整することから、第二実施例と同様な
効果を得ることができる。 Therefore, by controlling the opening and closing of the bypass valve 71 and the switching valve 73 as the outside temperature changes, one or two hot water heat exchangers are selectively operated, thereby reducing the circulating water of the station hot water system 91. Make rough adjustments to the temperature. Next, the cold water valve 51 and the hot water valve 5
Adjust the opening degree of No. 3 to set the circulating water temperature to a desired temperature that matches the outside air temperature. In this way, since the circulating water temperature is roughly adjusted by controlling the bypass valve 71 and the switching valve 73, the same effects as in the second embodiment can be obtained.
以上のように、特許請求の範囲第1項記載の発
明に係る原子力発電所の暖房システムは、原子炉
建屋内の暖房対象を暖房する閉ループの所内温水
系を有する原子力発電所の暖房システムにおい
て、上記所内温水系に配設され、原子炉冷却材浄
化系の非再生熱交換器からの熱量を受熱して上記
所内温水系の循環水を加熱する温水熱交換器と、
上記所内温水系に配設され、上記加熱された循環
水を循環させる温水ポンプと、上記所内温水系の
上記温水ポンプ上流側に配設されて冷水弁、温水
弁および制御演算部を備えた温度調整装置と、を
有し、上記温水弁は、上記温水熱交換器の下流側
に接続され、上記循環水のうちこの温水熱交換器
で加熱された温水を導びき、上記冷水弁は、上記
温水熱交換器を迂回するバイパス配管に配設され
て、上記循環水のうちこのバイパス配管を流れる
冷水を導びき、上記制御演算部は、外気温度検出
器並びに上記温水弁および冷水弁に接続され、上
記外気温度検出器からの信号に基づき上記両弁の
開度を調整して、上記冷水弁からの冷水流量と上
記水温弁からの温水流量とを変化させ、これら冷
水および温水が混合された混合水の流量を一定に
維持しつつ、その混合水の温度を外気温度に追従
して制御させたものである。また、特許請求の範
囲第2項記載の発明に係る原子力発電所の暖房シ
ステムは、原子炉建屋内の暖房対象を暖房する閉
ループの所内温水系を有する原子力発電所の暖房
システムにおいて、常時一定量の循環水が流れる
上記所内温水系に配設され、原子炉冷却材浄化系
の非再生熱交換器からの熱量を受熱して上記所内
温水系の循環水を加熱する温水熱交換器と、上記
所内温水系に配設され、上記加熱された循環水を
循環させる温水ポンプと、非再生熱交換器からの
排熱を上記温水熱交換器へ輸送する原子炉補機冷
却系に配設されて冷水弁、温水弁および制御演算
部を備えた温度調整装置とを有し、上記冷水弁
は、上記温水熱交換器の下流側に接続され、上記
非再生熱交換器から上記温水熱交換器へ導かれて
低温化された冷却水を冷水として導びき、上記温
水弁は、上記温水熱交換器を迂回するバイパス配
管に接続されて、上記非再生熱交換器から高温の
冷却水を温水として導びき、上記制御演算部は、
外気温度検出器並びに上記冷水弁および温水弁に
接続され、上記外気温度検出器からの信号に基づ
き上記両弁の開度を調整して上記冷水流量を変化
させることにより、外気温度に追従して上記循環
水温度を制御するものである。したがつて、上記
両発明ともに、温水ポンプの負荷変動幅を小とし
ポンプの運転性能を向上させて、システムの信頼
性向上、保守点検の容易化およびコストの低減を
図ることができるという効果を奏する。
As described above, the heating system for a nuclear power plant according to the invention set forth in claim 1 is a heating system for a nuclear power plant that has a closed-loop in-house hot water system that heats objects to be heated inside the reactor building. a hot water heat exchanger that is disposed in the station hot water system and receives heat from a non-regenerative heat exchanger of the reactor coolant purification system to heat circulating water of the station hot water system;
A hot water pump disposed in the station hot water system to circulate the heated circulating water, and a temperature pump disposed upstream of the hot water pump in the station hot water system and equipped with a cold water valve, a hot water valve, and a control calculation section. The hot water valve is connected to the downstream side of the hot water heat exchanger and guides the hot water heated by the hot water heat exchanger out of the circulating water, and the cold water valve is connected to the downstream side of the hot water heat exchanger, and the cold water valve is connected to the downstream side of the hot water heat exchanger. The controller is disposed in a bypass pipe that bypasses the hot water heat exchanger and guides cold water flowing through the bypass pipe among the circulating water, and the control calculation unit is connected to the outside air temperature detector and the hot water valve and the cold water valve. , the opening degrees of the two valves are adjusted based on the signal from the outside air temperature sensor to change the flow rate of cold water from the cold water valve and the flow rate of hot water from the water temperature valve, so that the cold water and hot water are mixed. The temperature of the mixed water is controlled to follow the outside temperature while maintaining the flow rate of the mixed water constant. Further, the heating system for a nuclear power plant according to the invention described in claim 2 is a heating system for a nuclear power plant that has a closed-loop in-house hot water system that heats objects to be heated inside the reactor building. a hot water heat exchanger disposed in the station hot water system through which circulating water flows, the hot water heat exchanger receiving heat from the non-regenerative heat exchanger of the reactor coolant purification system to heat the circulating water of the station hot water system; A hot water pump is installed in the station hot water system to circulate the heated circulating water, and a reactor auxiliary equipment cooling system is installed to transport waste heat from the non-regenerative heat exchanger to the hot water heat exchanger. a temperature adjustment device including a cold water valve, a hot water valve, and a control calculation unit, the cold water valve being connected downstream of the hot water heat exchanger, and connecting the non-regenerative heat exchanger to the hot water heat exchanger. The hot water valve is connected to a bypass pipe that bypasses the hot water heat exchanger to lead high temperature cooling water from the non-regenerative heat exchanger as hot water. The above control calculation section is
It is connected to an outside air temperature sensor, the cold water valve, and the hot water valve, and follows the outside air temperature by adjusting the opening degrees of both valves and changing the cold water flow rate based on the signal from the outside air temperature sensor. This is to control the temperature of the circulating water. Therefore, both of the above inventions have the effect of reducing the load fluctuation range of the hot water pump, improving the pump operating performance, improving system reliability, facilitating maintenance and inspection, and reducing costs. play.
また、温水熱交換器を二基設け、この温水熱交
換器を一基または二基選択的に作動させて所内温
水系の循環水温度を粗調整する場合には、温度調
整装置の温水弁および冷水弁の建全性を維持する
ことができる。 In addition, when two hot water heat exchangers are installed and the hot water heat exchangers are operated selectively to roughly adjust the circulating water temperature of the in-house hot water system, the hot water valve of the temperature adjustment device and The integrity of the cold water valve can be maintained.
さらに、流量調整弁を手動弁とした場合には、
この流量調整弁の故障が低減でき、暖房システム
の信頼性を向上させ、保守点検を簡易化し、さら
にコストの低減を図ることができる。 Furthermore, if the flow rate adjustment valve is a manual valve,
Failures of this flow rate regulating valve can be reduced, the reliability of the heating system can be improved, maintenance and inspection can be simplified, and costs can further be reduced.
第1図は従来の原子力発電所の暖房システムを
示す系統図、第2図は日本のある地方における一
日の最高および最低気温の通年変化を示すグラ
フ、第3図はこの発明に係る原子力発電所の暖房
システムの第一実施例を示す系統図、第4図は暖
房対象を所望温度に保つために必要な循環水温度
と外気温度との関係を示すグラフ、第5図ないし
第7図はこの発明に係る原子力発電所の暖房シス
テムの第二ないし第四実施例をそれぞれ示す系統
図である。
20,60,80,90……暖房システム、2
1,61,81,91……所内温水系、23……
原子炉冷却材浄化系、25,83,93……原子
炉補機冷却系、26……暖房対象、33……非再
生熱交換器、37……温水熱交換器、41……温
水ポンプ、43……入口弁、47,87……温度
調整装置、51……冷水弁、53……温水弁、5
5……制御演算器、57……外気温度検出器、6
3……第一温水熱交換器、65……第二温水熱交
換器。
Figure 1 is a system diagram showing the heating system of a conventional nuclear power plant, Figure 2 is a graph showing year-round changes in daily maximum and minimum temperatures in a certain region of Japan, and Figure 3 is a nuclear power plant according to the present invention. A system diagram showing the first embodiment of the heating system for a place, Figure 4 is a graph showing the relationship between the circulating water temperature and outside air temperature necessary to maintain the heating target at the desired temperature, and Figures 5 to 7 are FIG. 3 is a system diagram showing second to fourth embodiments of a heating system for a nuclear power plant according to the present invention. 20, 60, 80, 90... Heating system, 2
1, 61, 81, 91... In-house hot water system, 23...
Reactor coolant purification system, 25, 83, 93...Reactor auxiliary equipment cooling system, 26...Heating object, 33...Non-regenerative heat exchanger, 37...Hot water heat exchanger, 41...Hot water pump, 43...Inlet valve, 47, 87...Temperature adjustment device, 51...Cold water valve, 53...Hot water valve, 5
5...Control calculator, 57...Outside air temperature detector, 6
3...First hot water heat exchanger, 65...Second hot water heat exchanger.
Claims (1)
の所内温水系を有する原子力発電所の暖房システ
ムにおいて、上記所内温水系に配設され、原子炉
冷却材浄化系の非再生熱交換器からの熱量を受熱
して上記所内温水系の循環水を加熱する温水熱交
換器と、上記所内温水系に配設され、上記加熱さ
れた循環水を循環させる温水ポンプと、上記所内
温水系の上記温水ポンプ上流側に配設されて冷水
弁、温水弁および制御演算部を備えた温度調整装
置と、を有し、上記温水弁は、上記温水熱交換器
の下流側に接続され、上記循環水のうちこの温水
熱交換器で加熱された温水を導びき、上記冷水弁
は、上記温水熱交換器を迂回するバイパス配管に
配設されて上記循環水のうちこのバイパス配管を
流れる冷水を導びき、上記制御演算部は、外気温
度検出器並びに上記温水弁および冷水弁に接続さ
れ、上記外気温度検出器からの信号に基づき上記
両弁の開度を調整して、上記冷水弁からの冷水流
量と上記温水弁からの温水流量とを変化させ、こ
れら冷水および温水が混合された混合水の流量を
一定に維持しつつ、その混合水の温度を外気温度
に追従して制御させたことを特徴とする原子力発
電所の暖房システム。 2 温水熱交換器は2基からなり、1基または2
基の温水熱交換器により温水弁に導かれる温水と
しての循環水が加熱可能とされる特許請求の範囲
第1項記載の原子力発電所の暖房システム。 3 原子炉建屋内の暖房対象を暖房する閉ループ
の所内温水系を有する原子力発電所の暖房システ
ムにおいて、常時一定量の循環水が流れる上記所
内温水系に配設され、原子炉冷却材浄化系の非再
生熱交換器からの熱量を受熱して上記所内温水系
の循環水を加熱する温水熱交換器と、上記所内温
水系に配設され、上記加熱された循環水を循環さ
せる温水ポンプと、非再生熱交換器からの排熱を
上記温水熱交換器へ輸送する原子炉補機冷却系に
配設されて冷水弁、温水弁および制御演算部を備
えた温度調整装置とを有し、上記冷水弁は、温水
熱交換器の下流側に接続され、上記非再生熱交換
器から上記温水熱交換器へ導かれて低温化された
冷却水を冷水として導びき、上記温水弁は、上記
温水熱交換器を迂回するバイパス配管に接続され
て上記非再生熱交換器から高温の冷却水を温水と
して導びき、上記制御演算部は、外気温度検出器
並びに上記冷水弁および温水弁に接続され、上記
外気温度検出器からの信号に基づき上記両弁の開
度を調整して上記冷水流量を変化させることによ
り、外気温度に追従して上記循環水温度を制御す
ることを特徴とする原子力発電所の暖房システ
ム。 4 温水熱交換器は2基からなり、循環水は、1
基または2基の温水熱交換器を介して補機冷却系
の冷水としての冷却水により加熱可能とされる特
許請求の範囲第3項記載の原子力発電所の暖房シ
ステム。[Scope of Claims] 1. In a heating system for a nuclear power plant having a closed-loop in-house hot water system that heats objects to be heated in a reactor building, a non-regenerating reactor coolant purification system installed in the in-house hot water system is provided. a hot water heat exchanger that receives heat from the heat exchanger and heats circulating water in the station hot water system; a hot water pump that is disposed in the station hot water system and circulates the heated circulating water; a temperature adjustment device disposed upstream of the hot water pump in the hot water system and including a cold water valve, a hot water valve, and a control calculation section, the hot water valve being connected to the downstream side of the hot water heat exchanger. , the cold water valve is arranged in a bypass pipe that bypasses the hot water heat exchanger, and the cold water valve is arranged in a bypass pipe that bypasses the hot water heat exchanger, and the cold water valve flows through the bypass pipe. The control calculation unit is connected to an outside air temperature detector, the hot water valve, and the cold water valve, and adjusts the opening degrees of the two valves based on the signal from the outside air temperature detector, and controls the cold water valve. The flow rate of cold water from the hot water valve and the flow rate of hot water from the hot water valve are varied, and the temperature of the mixed water is controlled to follow the outside air temperature while maintaining the flow rate of the mixed water in which these cold water and hot water are mixed. A heating system for a nuclear power plant that is characterized by: 2 The hot water heat exchanger consists of two units, one or two
2. A heating system for a nuclear power plant according to claim 1, wherein circulating water as hot water guided to a hot water valve can be heated by a hot water heat exchanger. 3. In the heating system of a nuclear power plant that has a closed-loop in-house hot water system that heats the heating target inside the reactor building, the heating system is installed in the above-mentioned in-house hot water system through which a certain amount of circulating water always flows, and is installed in the reactor coolant purification system. a hot water heat exchanger that receives heat from a non-regenerative heat exchanger to heat circulating water in the in-house hot water system; a hot water pump that is disposed in the in-house hot water system and circulates the heated circulating water; a temperature adjustment device disposed in a reactor auxiliary cooling system for transporting waste heat from the non-regenerative heat exchanger to the hot water heat exchanger, and equipped with a cold water valve, a hot water valve, and a control calculation section; The cold water valve is connected to the downstream side of the hot water heat exchanger, and guides the cooled water that has been led from the non-regenerative heat exchanger to the hot water heat exchanger as cold water, and the hot water valve is connected to the hot water heat exchanger. connected to bypass piping that bypasses the heat exchanger to guide high-temperature cooling water from the non-regenerative heat exchanger as hot water, and the control calculation unit is connected to the outside air temperature detector and the cold water valve and hot water valve; The nuclear power plant is characterized in that the circulating water temperature is controlled in accordance with the outside air temperature by adjusting the opening degrees of the two valves and changing the cold water flow rate based on the signal from the outside air temperature detector. heating system. 4 The hot water heat exchanger consists of two units, and the circulating water is one
4. The heating system for a nuclear power plant according to claim 3, wherein heating is possible using cooling water as cold water of an auxiliary equipment cooling system via one or two hot water heat exchangers.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59020712A JPS60165597A (en) | 1984-02-09 | 1984-02-09 | Heating system of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59020712A JPS60165597A (en) | 1984-02-09 | 1984-02-09 | Heating system of nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60165597A JPS60165597A (en) | 1985-08-28 |
| JPH0521197B2 true JPH0521197B2 (en) | 1993-03-23 |
Family
ID=12034759
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59020712A Granted JPS60165597A (en) | 1984-02-09 | 1984-02-09 | Heating system of nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60165597A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2999693B1 (en) * | 2012-12-18 | 2015-06-19 | Air Liquide | REFRIGERATION AND / OR LIQUEFACTION DEVICE AND CORRESPONDING METHOD |
| FR3000541B1 (en) | 2013-01-03 | 2015-01-23 | Air Liquide | REFRIGERATION AND / OR LIQUEFACTION DEVICE AND CORRESPONDING METHOD |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56129919A (en) * | 1980-03-14 | 1981-10-12 | Matsushita Electric Ind Co Ltd | Controller for temperature of hot water supply |
| JPS57125899A (en) * | 1981-01-30 | 1982-08-05 | Tokyo Shibaura Electric Co | Atomic power plant |
| JPS57144499A (en) * | 1981-03-04 | 1982-09-07 | Hitachi Ltd | Nuclear reactor waste heat recovering device |
-
1984
- 1984-02-09 JP JP59020712A patent/JPS60165597A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60165597A (en) | 1985-08-28 |
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