JPH02602B2 - - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor water supply system that alleviates thermal shock during startup, shutdown, etc. Generally, a boiling water nuclear power generation facility using a boiling water reactor is constructed as shown in FIG. That is, numeral 1 in the figure is a reactor pressure vessel, and a reactor core is accommodated within this reactor pressure vessel 1. The steam generated within this reactor pressure vessel 1 is sent to a turbine 3 through a main steam pipe 2, drives this turbine 3, and generates electricity by a generator 4 connected to this turbine 3. It is composed of
The steam that drove the turbine 3 is transferred to a condenser 5
It is configured so that it is sent to and condensed. The condensate accumulated in the condenser 5 is sent by a low-pressure condensate pump 6 via an air extractor 7 and a grand steam condenser 8 to a condensate hyper-desalination device 9, where it is over-desalinated. It is configured to The condensate that has exited the condensate over-desalination device 9 is sent as feed water to the feed water heater 11 by a high-pressure condensate pump 10. Extracted steam from the turbine 3 is sent to this feedwater heater 11 via an extraction steam pipe 12, and the extracted steam and feedwater are heat exchanged to heat the feedwater to a predetermined temperature. has been done. This heated water supply is then pumped to the water supply pump 1.
3, the water is supplied into the reactor pressure vessel 1 via the main feedwater regulating valve 14 or, in the case of low flow rate, the low flow rate water supply regulating valve 15.
Further, 16 is a reactor coolant purification system. This reactor coolant purification system 16 includes a reactor recirculation pump 17
A portion of the reactor coolant, that is, reactor water is taken out from the suction side of the reactor, and is sent to the super desalinators 21a and 21b via the regenerative heat exchanger 19 and the non-regenerative heat exchanger 20 by the pump 18. It is configured. The high-temperature reactor water that has been sent is then heat-exchanged with the low-temperature reactor water from the super desalinators 21a and 21b in the regenerative heat exchanger 19, and the high-temperature reactor water that has been sent is cooled. At the same time, the low-temperature reactor water from the over-demineralizers 21a and 21b is heated. Then, the sent reactor water is further cooled in the non-regenerative heat exchanger 20 to a temperature lower than the heat resistance temperature of the ion exchange resin used in the super-demineralizers 21a and 21b.
a, 21b, where it is excessively desalted and purified. The purified reactor water is then transferred to the regenerative heat exchanger 1.
After being heated at 9, it is sent to a recombination tee 23 installed in the middle of the water supply pipe 22 between the main feed water regulating valve 14 and the reactor pressure vessel 1, where it is mixed with the feed water, and the reactor pressure is increased along with the feed water. It is configured to be returned into the container 1. By the way, when such boiling water nuclear power generation equipment is started or stopped, the generator 4 is not connected to the power transmission system, so no steam is sent to the turbine 3.
Steam generated in the reactor pressure vessel 1 is sent directly to the condenser 5 via the main steam bypass pipe 25 by opening the main steam bypass valve 24 and condensed. For this reason, extracted steam from the turbine 3 cannot be obtained, so heating of the feed water in the feed water heater 11 is stopped. Therefore, under such conditions, the reactor pressure vessel 1
The water supplied inside will be at a low temperature. Of course, since the reactor water from the reactor purification system 16 is mixed with the feed water in the recombination unit 23, the temperature of the feed water supplied into the reactor pressure vessel 1 is increased to some extent, but this reactor water is not recycled. Since the material cooled to below the heat resistance temperature of the ion exchange resin in the heat exchanger 20 is only heat exchanged in the regenerative heat exchanger 19, its temperature is not very high, and the flow rate is small. Even if such reactor water from the reactor coolant purification system 16 is mixed, the temperature of the feed water does not rise much. When such low-temperature water is supplied, high-cycle temperature fluctuations occur in the water supply nozzle, water supply spargeer, etc. inside the reactor pressure vessel 1, which applies thermal shock to these members and accumulates thermal fatigue. ,
This causes problems that impair the integrity of these members. In order to eliminate such problems, it would be possible to install a device that heats the feed water without depending on the steam extracted from the turbine 3 at startup or stop, but this would make the water supply system extremely complicated. This would require major modifications to the existing water supply system, which would be difficult to implement in practice. The present invention was made based on the above circumstances, and its purpose is to be able to heat the feed water even during startup or shutdown, and to maintain the integrity of the reactor pressure vessel without causing thermal shock to the members inside the reactor pressure vessel. without complicating the water supply system.
Another objective is to obtain reactor water supply equipment that can be implemented by simply making minor modifications to existing equipment. The present invention will be described below with reference to an embodiment shown in FIGS. 2 to 4. In the figure, 101 is a reactor pressure vessel, and this reactor pressure vessel 101 is housed in a reactor containment vessel 102. Also,
A reactor core (not shown) is housed within this reactor pressure vessel 101 . A main steam pipe 103 is connected to this reactor pressure vessel 101, and this main steam pipe 103 penetrates the reactor containment vessel 102.
It is connected to the turbine 104. In the middle of this main steam pipe 103, there are main steam isolation valves 105a and 105 installed inside and outside the reactor containment vessel 102.
b is provided, and a main steam stop valve 106 and a steam control valve 107 are provided near the turbine 104. The steam generated in the reactor pressure vessel 101 is sent to the turbine 104 through the main steam pipe 103 to drive the turbine 104, and the generator 1 connected to the turbine 104 drives the turbine 104.
07 to generate electricity.
The steam that drove this turbine 104 is then sent to a condenser 108. In this condenser 108, a cooling water source 109 is supplied to the condenser cooling water circulation pump 1.
Heat exchange is performed between the cooling water sent by 10 and the above-mentioned steam, and the steam is condensed to form condensate water. In addition, the above main steam pipe 103
A main steam bypass pipe 111 is provided branching off from the main steam bypass pipe 111, and this main steam bypass pipe 111 directly communicates with the above-mentioned condenser 108, and a main steam bypass valve 112 is provided in the middle thereof. . When starting or stopping this equipment, the generator 1
07 is not included in the power transmission system, the main steam stop valve 106 is closed, the main steam bypass valve 112 is opened, and the reactor pressure vessel 101 is closed.
The steam generated in the main steam bypass pipe 111
The condenser 108 is configured to release the water to the condenser 108 via the condenser 108. The condensate accumulated in the condenser 108 is pumped to an air extractor 114 by a low pressure condensate pump 113.
It is then sent to an over-desalination device 116 via a gland steam condenser 115, where solid impurities are over-removed and dissolved impurities are removed using an ion exchange resin or the like. The condensate from which this impurity has been removed is sent to the high pressure condensate pump 11.
The pressure is increased by 7, and the feed water heater 11 is used as the feed water.
8. Extracted steam from the turbine 104 is sent to this feedwater heater 118 via an extraction steam pipe 119, and the feedwater is heated to a predetermined temperature by the extracted steam. Then, this heated feed water is supplied to the reactor pressure vessel 1 by a feed water pump 120 via a main feed water regulating valve 121 or a low flow water supply regulating valve 122 provided in parallel therewith.
01. still,
Although only one water supply pump 120 is shown in the figure, this is for convenience to simplify the diagram, and in reality, for example, a plurality of water supply pumps are arranged in parallel. The driving source thereof is usually a steam turbine for a water supply pump (not shown), and a motor-driven one, for example, is installed as a backup. Driving steam is supplied to the steam turbine through a steam pipe (not shown) branched from the main steam pipe 103.
The main water supply regulating valve 121 and the low flow water supply regulating valve 122 are configured to be controlled by a control device 123. This control device 12
3, a main steam flow rate detector 124 provided in the middle of the main steam pipe 103, and a main water supply regulating valve 121.
It receives signals from a water supply flow rate detector 126 provided in the middle of the water supply pipe 125 between the reactor pressure vessel 101 and the water level detector 127 that detects the water level in the reactor pressure vessel 101, and Basically, the opening degree of the main water supply adjustment valve 121 or the low flow rate water supply adjustment valve 122 is adjusted to adjust the flow rate of the supplied water supply. Also, 12
8 is a reactor coolant purification system. 129 is a branch pipe of this reactor coolant purification system 128 , and this branch pipe 129 is connected to the suction side of a recirculation pump 130 of a recirculation system 170 that recirculates reactor water in the reactor pressure vessel 101. and recirculation system 170
A portion of the reactor water taken out by the reactor is sent to the circulation pump 131 of the reactor coolant purification system 128 . The reactor water sent to the circulation pump 131 is sent to the primary side of the regenerative heat exchanger 133 via the regenerative heat exchanger inlet valve 132, and further via the non-regenerative heat exchanger 134 to the super-demineralizer 135.
a, 135b.
The reactor water that has exited these over-desalinators 135a and 135b is sent to the secondary side of the regenerative heat exchanger 133, and further passes through the regenerative heat exchanger outlet valve 136 and the reactor water return piping 171 to the main Water supply adjustment valve 1
21 and the reactor pressure vessel 101
The water is sent to a recombination tea 137 provided in the middle of the reactor pressure vessel 101, mixed with feed water, and returned to the reactor pressure vessel 101. This reactor water is first cooled in the regenerative heat exchanger 133 by exchanging heat with the low-temperature reactor water from the super-desalinators 135a and 135b.
The temperature of the reactor water from 35a and 135b is increased, and the non-regenerative heat exchanger 134 is used to further demineralize the reactor water.
It is cooled to a temperature below the allowable heat resistance temperature of the ion exchange resin used in 5b. This cooled reactor water is purified by passing through demineralizers 135a and 135b to remove solid impurities and removing dissolved impurities. After the temperature is raised, it is mixed with the feed water. In addition, the over-demineralizer 135a, 1
35b is equipped with two units rated at 50% of the total purification capacity required. Further, a bypass pipe 138 is provided that communicates the discharge side of the reactor coolant purification system circulation pump 131 with the downstream side of the regenerative heat exchanger outlet valve 136.
A bypass valve 139 is provided in the middle of the valve 8. Therefore, by opening this bypass valve 139, the reactor water from the recirculation system 170 is returned to the reactor without passing through the regenerative heat exchanger 133, the non-regenerative heat exchanger 134, and the excessive desalination devices 135a and 135b. It is configured to flow into piping 171. The water supply system configured as described above is provided with a water supply system feed water heating mechanism 140 that can heat the feed water even when heating of the feed water by the feed water heater 118 stops, such as when starting or stopping. . The configuration will be explained below. A water pump recirculation pipe 141 communicates the discharge side and the suction side of the water pump 120 through the water pump recirculation pipe 141. And this water pump recirculation pipe 14
1, a water pump recirculation valve 142 is provided. In addition, this water pump recirculation pipe 141
A minimum flow pipe 143 is provided branching off from the middle, and this minimum flow pipe 143 communicates with the condenser 108 described above. A minimum flow valve 1 is installed in the middle of this minimum flow pipe 143.
44 are provided. When the feed water heating by the feed water heater 118 stops, such as when starting or stopping, the minimum flow valve 144 is closed and the water pump recirculation valve 142 is opened to connect the water pump 120 and the water pump recirculation pipe. 141 to form a feed water recirculation loop, and the feed water is configured to be able to be circulated within this recirculation loop. Therefore, the feed water circulating in this recirculation loop is configured to be heated to a predetermined temperature by converting the power of the feed water pump 120 into thermal energy each time it passes through the feed water pump 120. has been done. Then, this heated feed water is continuously taken out in the required amount from the recirculation loop and supplied into the reactor pressure vessel 101, and only an amount corresponding to this taken out amount is sent to the condenser 10.
New feed water is continuously supplied into this recirculation loop from within 8, and the feed water can be heated even when the feed water heater 118 stops heating the feed water. Further, the water pump recirculation valve 142 and the minimum flow valve 144 are configured to be automatically controlled to open and close by a control circuit 145. The control circuit 145 is configured as shown in FIG. 3 and is provided on the suction side of the water supply pump 120, including a flow rate detector 146 for detecting the inlet flow rate of the water supply pump 120, and a temperature detector 146 for detecting the inlet temperature of the water supply pump 120. 147, the operation switch 148 of the minimum flow valve 144, the operation switch 149 of the water supply pump recirculation valve 142, etc., and the minimum flow output from the water supply system control device (not shown) in response to the equipment status. It is configured such that a valve opening signal or a valve closing signal of the valve 144 is input. The minimum flow valve opening command signal from the water supply system control device and the valve opening signal from the minimum flow valve operation switch 148 are input to the OR circuit 150, and the OR circuit 1
The output from 50 is configured to be sent to the minimum flow valve 144 as a valve opening signal for the minimum flow valve 144. Therefore, the minimum flow valve 144 is configured to be opened only when a valve opening command signal is output from the water supply system control device or when the minimum flow valve operation switch is manually switched to open. Further, the minimum flow valve 144 is configured to output a signal when the valve is open, and this signal is input to the AND circuit 151. Also, minimum flow valve operation switch 1
48 is switched to automatic and a signal output when the water pump recirculation valve 142 is fully opened are respectively input to the AND circuit 151. The output of this AND circuit 151 is the OR circuit 152.
The output of this OR circuit 152 is configured to be sent to the minimum flow valve 144 as a valve closing signal for the minimum flow valve 144. Further, the signal output when the minimum flow valve operation switch 148 is automatically switched and the valve closing command signal of the minimum flow valve 144 from the water supply system control device are input to an AND circuit 153, and the output of this AND circuit 153 is It is configured to be input to the OR circuit 152 described above. Therefore, this minimum flow valve 144 is mutually connected to the water pump recirculation valve 142 so that the minimum flow valve operating switch 148 is automatically switched and the water pump recirculation valve 142 is closed when the water pump recirculation valve 142 is opened. The valve is also closed when the minimum flow valve operating switch 148 is automatically switched and a valve closing command signal is output from the water supply system control device. Further, the signal output when the minimum flow valve operation switch 148 is automatically switched and the signal output when the water pump recirculation valve operation switch 149 is closed are sent to an AND circuit 154, The output of the circuit 154 is input to an OR circuit 155, and the output of the OR circuit 155 is configured to be sent to the water pump recirculation valve 142 as a valve closing signal. Further, when the inlet water temperature of the water supply pump 120 detected by the temperature detector 147 falls below T°C, which is the temperature during rated operation, a signal is output, and this signal is sent to the The signal is configured to be input to circuit 155. Therefore, the minimum flow valve operation switch 148 is automatically switched to this water supply pump recirculation valve 142, the water supply pump recirculation valve operation switch 149 is switched to close, and the water supply pump 1
The valve is closed when the inlet water supply temperature of the water supply pump 120 is below T°C, and the valve is closed when the inlet water supply temperature of the water supply pump 120 is below T°C.
The valve is configured to automatically close when the temperature exceeds ℃. Also, a signal when the above-mentioned minimum flow valve operation switch 148 is switched to automatic, a signal when the water supply pump recirculation valve operation switch 149 is switched to open, a signal when the inlet feed water temperature of the water supply pump 120 is below T°C. The signal and the signal when the inlet water supply flow rate of the water supply pump 120 is less than X%, which is the flow rate when the generator 107 is connected, are respectively input to the AND circuit 157, and the output of this AND circuit 157 is the water supply flow rate. The signal is configured to be sent to the pump recirculation valve 142 as a valve opening signal. Therefore, this water pump recirculation valve 142 is operated by the minimum flow valve operation switch 14.
8 is switched to automatic, the water pump recirculation valve operation switch 149 is switched to open, and the valve opens only when the inlet water supply temperature of the water supply pump 120 is below T°C and the inlet water supply flow rate is below X%. be done. Therefore, by this control circuit 145, the minimum flow valve 144 receives a command signal from the water supply system control device and the minimum flow valve operating switch 14.
8, the opening and closing are controlled in the same way as in the conventional case, and the water supply pump 120 is protected by securing the minimum flow rate necessary for operation of the water supply pump 120. In addition, when the inlet water supply temperature of the water supply pump 120 is equal to or higher than T°C during rated operation, or when the inlet water supply flow rate is X%, which is the flow rate when the generator 107 is connected,
In the above case, the water supply pump recirculation valve 142 is configured not to open, and the water supply pump recirculation valve 14 is configured so that the water supply pump recirculation valve 142 is not opened unless a valve closing command signal for the minimum flow valve 144 is given from the water supply system control device.
The minimum flow valve 144 is configured not to close unless the valve 2 is opened. Further, the reactor coolant purification system 128 is also provided with a purification system feed water heating mechanism 158 that can heat the feed water during startup or shutdown, and the configuration thereof will be described below. Reference numeral 159 denotes a temperature detector, which is installed in the water supply pipe 125 between the main water supply regulating valve 121 and the reactor pressure vessel 101 and measures the temperature of the water supply supplied into the reactor pressure vessel 101. is configured to detect. Further, 160 is a control circuit, and the signal from the temperature detector 159 is transmitted to this control circuit 160.
The control circuit 160 is configured to control the opening and closing of the bypass valve 139 of the reactor coolant purification system 128 based on the signal from the temperature detector 159. And this control circuit 1
60 is constructed as shown in FIG. 161
is a feed water temperature setting device and is a reactor pressure vessel 101
The device is configured to output a signal corresponding to a set value of the temperature of the water supplied to the inside. The signal from this feed water temperature setting device 161 is configured to be sent to an adder 162. Further, the signal from the temperature detector 159 is input to the adder 162, which is configured to obtain a deviation signal between the set value of the feed water temperature and the actual feed water temperature. This deviation signal is transmitted to contact 16 of interlock relay 163.
4 to an upper and lower limiter 165, and is further sent to an electro-pneumatic converter 167 via an integrator 166. The electro-pneumatic converter 167 is configured to convert the deviation signal into an air signal and send it to the bypass valve 139, and to control the opening and closing of the bypass valve 139 in response to the deviation signal. The upper and lower limit limiters 165 regulate the upper and lower limits of the deviation signal to prevent sudden opening and closing of the bypass valve 139, and the integrator 166
is to open and close the bypass valve 139 at a constant speed by integrating the deviation signal. Further, an autobalance contact 168 of the interlock relay 163 is provided to bypass the upper and lower limiter 165 and the integrator 166. This interlock relay 163 is connected to the reactor coolant purification system 12.
Only when at least one of the eight over-demineralizers 135a and 135b is stopped and isolated, it is manually energized to close the contact 164 and open the autobalance contact 168. Therefore, when this interlock relay 163 is energized, a deviation signal is sent to the electro-pneumatic converter 1.
67, the bypass valve 139 opens in response to this deviation signal, and the high-temperature reactor water taken out from the suction side of the reactor recirculation pump 130 flows into the bypass pipe 1.
38 and is sent to the recombination tea 137 in a high temperature state where it is mixed with the feed water, and the feed water is heated to a set temperature set by the feed water temperature setting device 161. In addition, when the flow rate of reactor water required to flow through the bypass pipe 138 in order to raise the temperature of the feed water to the set temperature is relatively small, only one of the over-desalinators 135a and 135b is shut down and isolated. It is controlled so that both are shut down and isolated only when the flow rate becomes too large, so that the purification function of the reactor coolant is not impaired as much as possible. In one embodiment of the present invention configured as described above, the reactor pressure vessel 1 is
Steam generated in the main steam bypass pipe 103
If extracted steam from the turbine 104 is no longer obtained and feedwater heating by the feedwater heater 118 stops, the feedwater pump recirculation valve 1 of the feedwater system feedwater heating mechanism 140 is bypassed to the condenser 108 via the
42 and the minimum flow valve 144.
is closed to form a feed water recirculation loop with the feed water pump 120 and the feed water pump recirculation pipe 141, and the feed water pump 120 is operated at a relatively large output to circulate the feed water within this recirculation loop. Since various losses of the water supply pump 120 are ultimately converted into heat, the temperature of the water supply is increased each time it passes through the water supply pump 120, and is heated to a predetermined temperature.
Then, the feed water heated to a predetermined temperature is taken out little by little from this recirculation loop to the reactor pressure vessel 1.
01 and a corresponding amount of feedwater is fed into this recirculation loop. Note that when feedwater heating by the feedwater heater 118 is stopped, the flow rate of feedwater supplied to the reactor pressure vessel 101 is generally small, so if the feedwater pump 120 is operated at a relatively high output, the amount of water inside the reactor pressure vessel 101 will be reduced. The flow rate circulating within this recirculation loop can be much greater than the feed water flow rate supplied or withdrawn from this recirculation loop. Therefore, the feed water supplied into this recirculation loop will be circulated within this recirculation loop many times before being taken out from this recirculation loop, and the temperature at which it passes once through the feed water pump 120 will decrease. Even if the rise is small, it can be heated to a predetermined high temperature by passing through it many times. Therefore, the feed water heater 118
Even if the heating of the feed water is stopped, the feed water supplied to the reactor pressure vessel 101 can be heated to a predetermined temperature, and thermal shock is prevented from being applied to the water supply nozzle, the water supply spargeer, etc. in the reactor containment vessel 101. , without damaging the integrity of these members. In addition, if the water supply system feed water heating mechanism 140 is insufficient to raise the temperature of the supply water, the interlock relay 163 of the control circuit 160 of the purification system feed water heating mechanism 158 is energized to open the bypass valve 139. The high-temperature reactor water is then sent directly to the recombination tea 137 where it is mixed with feed water, and the temperature of this feed water can be raised to a set temperature. Further, the water supply system feed water heating mechanism 140 is controlled by the water feed pump recirculation valve 142 by the control circuit 145.
Since the minimum flow valve 144 is controlled together with the minimum flow valve 144, for example, the minimum flow valve 144 is controlled in the same manner as before by the command signal of the water supply system control device and the operation of the minimum flow valve operation switch 148, and the required minimum flow rate of the water supply pump 120 can be ensured. . In addition, when the inlet water supply temperature of the water supply pump 120 is equal to or higher than T°C during rated operation, or when the inlet water supply flow rate is equal to or higher than X% when the generator is connected, the water supply pump recirculation valve 142
Opening the valve to recirculate the feedwater may further heat the feedwater, raising its temperature excessively or causing excessive feedwater flow through the feedwater pump 120, potentially damaging the feedwater pump 120. However, due to this control circuit 145, the feed water pump recirculation valve 142 is not opened unless the inlet feed water temperature of the feed water pump 120 is T°C and the inlet feed water flow rate is below X%, so the water feed pump 120 may be damaged as described above. is definitely prevented. Furthermore, if both the water supply pump recirculation valve 142 and the minimum flow valve 144 are closed, the minimum flow rate of the water supply pump 120 may not be ensured. The minimum flow valve 144 is otherwise interlocked to close only when the water pump recirculation valve 142 is open, thereby ensuring that the minimum flow rate of the water pump 120 is maintained. . Note that the present invention is not limited to the above embodiment. For example, the control circuit for the feedwater heating mechanism of the water supply system is not necessarily limited to the one described above. As described above, the present invention provides a signal to open the bypass valve of the bypass pipe based on a signal from a temperature detector provided in the water supply pipe when the temperature of the water supply supplied into the reactor pressure vessel falls below a predetermined temperature. is sent out from the control means, and the reactor water from the recirculation system flows into the water supply pipe through the bypass pipe and the reactor water return pipe, so the temperature of the feed water can be raised by the reactor water. Therefore, even when the feedwater heater stops heating the feedwater, the feedwater supplied to the reactor pressure vessel can be heated to a predetermined temperature, and thermal shock is prevented from being applied to the water supply nozzle and the water supply spurt inside the reactor pressure vessel. However, it does not impair the integrity of these members, has a simple configuration, and can be implemented with only minor modifications to existing equipment, which has great effects.

[Brief explanation of drawings]

FIG. 1 is an overall system diagram of a conventional example. Figures 2 to 4 show one embodiment of the present invention, Figure 2 is an overall system diagram, Figure 3 is a circuit diagram of the control circuit of the water supply system feed water heating mechanism, and Figure 4 is a purification system feed water heating system. FIG. 3 is a circuit diagram of a control circuit of the mechanism. 101... Nuclear reactor pressure vessel, 104... Turbine,
108... Condenser, 112... Main steam bypass valve, 1
18... Water supply heater, 120... Water supply pump, 125
... Water supply pipe, 128 ... Reactor coolant purification system, 140
...Water supply system feed water heating mechanism, 141...Water pump recirculation pipe, 142...Water pump recirculation valve, 144...Minimum flow valve, 145...Control circuit, 158 ...Purification system feed water heating mechanism.

Claims (1)

[Claims] 1. A feedwater heater that heats feedwater with steam extracted from the turbine, a feedwater pump that supplies the feedwater heated by the feedwater heater into the reactor pressure vessel via a water supply pipe, and the reactor pressure vessel mentioned above. a recirculation system that recirculates the reactor water within the reactor; a reactor coolant purification system that is connected to the recirculation system and purifies the reactor water; and a reactor coolant purification system that purifies the reactor water through the water supply pipes. A reactor water return pipe that returns to the reactor pressure vessel, a bypass pipe that allows the reactor water to bypass the purification system and flow to the reactor water return pipe, a bypass valve provided on the bypass pipe, and the water supply pipe. 1. A nuclear reactor water supply facility comprising: a temperature detector provided in the temperature detector; and a control means for controlling opening and closing of the bypass valve based on a signal from the temperature detector.