JPH1138174A - Residual heat removal device - Google Patents

Abstract

PROBLEM TO BE SOLVED: To ease thermal shock receiving from a reactor water in a reactor pressure vessel by returning a part of reactor water of a by-pass system via a head spray system to the reactor pressure vessel and merging the remaining reactor water in the by-pass system to the reactor water cooled by a core water cooling system. SOLUTION: The residual heat removal device 20 is provided to a reactor pressure vessel 21 and is connected as a continuous one body to a reactor recirculation system 23 provided with a recirculation pump 22 and a head spray system 25 provided with a flow control valve 24. The reactor water supplied to a by-pass valve 30 is flow-controlled at a flow control valve 27 and a part of it is returned via a head spray system 25 to the reactor pressure vessel 21 and the remaining part merges into the reactor water as cooling water from a non-reproducible heat exchanger 28 via a check valve 31 and controlled here to cooling water at proper temperature. The reactor water from the by-pass system 32 and the reactor water as cooling water from a cooling water cooling system 29 merge and the merged water is returned to the reactor pressure vessel 21.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a residual heat removing apparatus applied to a nuclear power plant, and more particularly, to reactor water heated by decay heat and residual heat generated in a reactor core when the reactor is shut down or shut down. The present invention relates to a residual heat removing device for taking out the reactor water, cooling the reactor water to an appropriate temperature, and returning the reactor water to the reactor.

[0002]

2. Description of the Related Art In a boiling water nuclear power plant, when the reactor is stopped, a head spray operation is sometimes performed to shorten the cooling time, and the temperature drop of the reactor pressure vessel may be rapidly promoted. The spray water for performing the head spray operation is taken from the reactor core, and the taken high-temperature reactor water is cooled to an appropriate temperature by a residual heat removal device (hereinafter referred to as RHR system) and returned to the reactor core. FIG. 13 shows a system configuration.

[0003] The RHR system 1 is provided in the reactor pressure vessel 4 and is connected to the reactor recirculation system 3 equipped with a recirculation pump 7 and the head spray system 2 equipped with a flow control valve 10 as a continuous unit. RHR pump 6, flow control valve 9
And a reactor water cooling system 11 having a regenerative heat exchanger 5, a bypass system 12 having a bypass valve 8, and a cooling reactor water return system 13. A part of the reactor water from the reactor pressure vessel 4 taken in at 7 is pressurized by the RHR pump 6 and is supplied to the cooling water return system 1 via the non-regenerative heat exchanger 5 of the reactor water cooling system 11 or the bypass system 12.
3 and is returned to the reactor pressure vessel 4 via the head spray system 2 and the reactor recirculation system 3.

[0004] Further, since the RHR system 1 has its pipe system maintained at a temperature slightly higher than room temperature, when the recirculation pump 7 of the reactor recirculation system 3 performs a rated operation during the start-up operation, a high temperature is generated. Reactor water gives a thermal shock to the tubing.

For this reason, the RHR system 1 includes a recirculation pump 7
Is operated intermittently so that the temperature of the reactor water passing through the pipe system does not suddenly change.

[0006]

As described above, the RHR system 1 uses the recirculation pump 7 to recirculate the reactor water in the reactor pressure vessel 4 in order to shorten the cooling time of the reactor pressure vessel 4 when the reactor is stopped. The reactor water is cooled intermittently by the non-regenerative heat exchanger 5, and the cooling water is returned to the reactor pressure vessel 4 via the cooling water return system 13 and the head spray system 2. However, during the intermittent operation of the recirculation pump 7, the recirculation pump 7 malfunctions for some reason and becomes longer than a predetermined operation time, and an excessive amount of reactor water flows to the non-regenerative heat exchanger 5, where it is generated. In some cases, the amount of cooling water to be supplied exceeds the flow rate required by the head spray system 2.

As described above, when the amount of the cooling water becomes excessive, a large temperature difference is generated between the cooling water and the reactor water. Due to the thermal stress generated locally due to the temperature difference, the reactor pressure vessel 4 There was a possibility that the soundness of maintaining the strength of the steel might be lost.

Further, making the recirculation pump 7 perform the intermittent operation gives material fatigue to the pump shaft and the impeller, making it difficult to maintain the material strength for a long time. Deterioration is caused, and it is also a factor of causing malfunction.

The present invention has been made in view of such circumstances, and has a recirculation pump that performs continuous operation from the start-up, and a reactor water cooling system and a bypass system of an RHR system are used in combination, and the reactor pressure is reduced. It is an object of the present invention to provide a residual heat removing device that adjusts reactor water taken from a vessel to an appropriate temperature and returns the reactor water to a reactor pressure vessel.

[0010]

According to a first aspect of the present invention, there is provided a residual heat removing apparatus for removing water from a reactor pressure vessel via a reactor recirculation system. A residual heat removal device that includes a bypass system juxtaposed to the reactor water cooling system that cools the reactor water, and returns one of the reactor water cooled by the reactor water cooling system and the reactor water of the bypass system to the reactor pressure vessel. In, while a part of the reactor water of the bypass system is returned to the reactor pressure vessel via the head spray system, the remaining reactor water of the bypass system is combined with the reactor water cooled by the reactor water cooling system, and A cooling water return system for returning to the reactor pressure vessel is provided.

In order to achieve the above object, a residual heat removing apparatus according to the present invention cools reactor water taken from a reactor pressure vessel via a reactor recirculation system. A residual heat removal device for returning one of the reactor water cooled by the reactor water cooling system and the reactor water of the bypass system to the reactor pressure vessel, comprising a bypass system juxtaposed with the reactor water cooling system; A part of the reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining reactor water of the bypass system is combined with the reactor water cooled by the reactor water cooling system and returned to the reactor pressure vessel. A cooling water return system, and a temperature buffer provided between the reactor recirculation and the cooling water system.

In order to achieve the above object, the residual heat removing device according to the present invention is characterized in that the temperature buffer device is a water storage tank.

[0013] In order to achieve the above object, the residual heat removing device according to the present invention, as described in claim 4, wherein the water storage tank has an inlet nozzle and an outlet nozzle. It is installed with a head formed at a distance.

In order to achieve the above object, in the residual heat removing apparatus according to the present invention, the water storage tank has an air layer formed on a free surface of the reactor water.

In order to achieve the above object, in the residual heat removing apparatus according to the present invention, the water storage tank is provided with a pressurizer.

In order to achieve the above object, in the residual heat removing device according to the present invention, the inlet nozzle of the water storage tank is formed with a slit.

In order to achieve the above object, a residual heat removing apparatus according to the present invention cools reactor water taken from a reactor pressure vessel via a reactor recirculation system. A residual heat removal device for returning one of the reactor water cooled by the reactor water cooling system and the reactor water of the bypass system to the reactor pressure vessel, comprising a bypass system juxtaposed with the reactor water cooling system; A part of the reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining reactor water of the bypass system is combined with the reactor water cooled by the reactor water cooling system and returned to the reactor pressure vessel. A cooling water return system, and a non-regenerative heat exchanger provided between the reactor recirculation and the cooling water system.

In order to achieve the above object, in the residual heat removing apparatus according to the present invention, the non-regenerative heat exchanger includes a non-regenerative heat exchanger bypass system. .

In order to achieve the above object, the residual heat removing apparatus according to the present invention cools reactor water taken from a reactor pressure vessel via a reactor recirculation system. A residual heat removal device for returning one of the reactor water cooled by the reactor water cooling system and the reactor water of the bypass system to the reactor pressure vessel, comprising a bypass system juxtaposed with the reactor water cooling system; A part of the reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining reactor water of the bypass system is combined with the reactor water cooled by the reactor water cooling system and returned to the reactor pressure vessel. While providing a non-regenerative heat exchanger between the cooling water return system and the reactor recirculation and the cooling water system, the non-regenerative heat exchanger includes a non-regenerative heat exchanger bypass system, Drive the residual heat removal pump of the reactor water cooling system A motor for those incorporating the inverter circuit.

In order to achieve the above object, a residual heat removing apparatus according to the present invention cools reactor water taken from a reactor pressure vessel via a reactor recirculation system, as described in claim 11. A residual heat removal device for returning one of the reactor water cooled by the reactor water cooling system and the reactor water of the bypass system to the reactor pressure vessel, comprising a bypass system juxtaposed with the reactor water cooling system; Returning a reactor water to the reactor pressure vessel via a head spray system, and controlling a flow rate of the reactor water cooled by the reactor water cooling system to supply the reactor water to the head spray system; and a flow control valve for the reactor water cooling system. And a flow rate control valve for controlling the flow rate of the reactor water cooled in step 2 and returning the reactor water from the cooling water return system to the reactor pressure vessel.

In order to achieve the above object, a residual heat removing apparatus according to the present invention cools reactor water taken from a reactor pressure vessel via a reactor recirculation system. A residual heat removing device for returning either the reactor water cooled by the reactor water cooling system or the reactor water of the bypass system to the reactor pressure vessel. A first sub-bypass system is provided in the system, and a second sub-bypass system is provided in the bypass system.

In order to achieve the above object, the apparatus for removing residual heat according to the present invention cools reactor water taken from a reactor pressure vessel via a reactor recirculation system. A residual heat removal device for returning one of the reactor water cooled by the reactor water cooling system and the reactor water of the bypass system to the reactor pressure vessel, comprising a bypass system juxtaposed with the reactor water cooling system; A part of the reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining reactor water of the bypass system is combined with the reactor water cooled by the reactor water cooling system and returned to the reactor pressure vessel. A cooling water return system and a temperature buffer between the reactor recirculation and the cooling water system are provided, while the cooling water return system is connected to the temperature buffer.

In order to achieve the above object, the apparatus for removing residual heat according to the present invention cools reactor water taken from a reactor pressure vessel via a reactor recirculation system. In the residual heat removing apparatus, a bypass system is provided in parallel with the reactor water cooling system, and either the reactor water cooled in the reactor water cooling system or the reactor water in the bypass system is returned to the reactor pressure vessel. A regenerative heat exchanger is provided between the circulation system and the reactor water cooling system, and the reactor water cooled by the reactor water cooling system is combined with the reactor water of the bypass system. A cooling furnace water return system is provided for supplying the rest of the combined water to the regenerative heat exchanger while returning the combined water to the furnace pressure vessel.

[0024]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of a residual heat removing apparatus according to the present invention will be described below with reference to the drawings and the part numbers attached to the drawings.

FIG. 1 is a schematic system diagram showing a first embodiment of the residual heat removing apparatus according to the present invention.

A residual heat removal apparatus 20 (hereinafter, referred to as an RHR system) according to the present embodiment is provided in a reactor pressure vessel 21 and includes a reactor recirculation system 23 having a recirculation pump 22 and a flow control valve 24. Is connected continuously to the head spray system 25 provided with

Further, the RHR system 20 includes the reactor pressure vessel 2
RHR pump 26 for increasing the pressure of the reactor water taken in from reactor 1 by recirculation pump 22 of reactor recirculation system 23, flow rate regulating valve 27 for cooling part of the reactor water, and reactor water including non-regenerative heat exchanger 28 A cooling system 29, a bypass valve 30 having a non-return valve 31, a bypass valve 30 having a bypass valve 30 for bypassing the remainder of the reactor water with the reactor water cooled by the non-regenerative heat exchanger 28, A cooling water return system 33 is provided for merging reactor water as cooling water of the reactor water cooling system 29 to an appropriate temperature and returning the combined water to the reactor pressure vessel 21 via the reactor recirculation system 23. .

The RHR system 20 having such a configuration is
During shutdown operation of the reactor pressure vessel 21, the reactor pressure vessel 21
A part of the reactor water continuously taken in by the recirculation pump 22 of the reactor recirculation system 23 is bypassed from the RHR pump 26
To the reactor water cooling system 29 and the bypass system 30.

The flow rate of the reactor water supplied to the reactor water cooling system 29 is controlled by a flow control valve 27, and the non-regenerative heat exchanger 2
Cooled at 8.

The flow rate of the reactor water supplied to the bypass system 30 is controlled by a flow control valve 27, and a part of the reactor water is supplied via the head spray system 25 to the reactor pressure vessel 21.
And the remaining part is combined with the reactor water as the cooling water from the non-regenerative heat exchanger 28 via the check valve 31, where the cooling water is adjusted to the appropriate temperature. The reactor water from the bypass system 32 and the reactor water as the cooling water from the reactor water cooling system 29 are merged, and the merged water adjusted to an appropriate temperature passes through the cooling water return system 33 and the reactor recirculation system 23. And returned to the reactor pressure vessel 21. The rate of temperature decrease of the reactor water cooled by the non-regenerative heat exchanger 28 is adjusted by the opening degree of the flow control valve 27.

As described above, in this embodiment, the RHR system 2
The cooling water 29 from the reactor water cooling system 29 is used as the cooling water from the reactor water cooling system 29 and the bypass system 3
Since the reactor water from the reactor water 2 is joined and the combined water is returned to the reactor pressure vessel 21 at an appropriate temperature, the thermal shock of the reactor pressure vessel 21 received from the reactor water can be suppressed lower than before.

Therefore, according to the present embodiment, when the reactor pressure vessel 21 is stopped, the recirculation pump 22 of the reactor recirculation system 23 is continuously operated to adjust the cooling of the RHR system water to an appropriate temperature. Since the so-called shutdown cooling operation is performed, the reactor water is supercooled based on the intermittent operation of the recirculation pump 22 as in the related art, without causing an unexpected accident. , Quick and stable operation can be performed.

FIG. 2 is a schematic system diagram showing a second embodiment of the RHR system according to the present invention. Note that the same reference numerals are given to portions that are the same as or correspond to the components of the first embodiment.

In this embodiment, a reactor water temperature buffer 34 is provided between the recirculation pump 22 of the reactor recirculation system 23 and the RHR pump 26 of the RHR system 20.

As shown in FIG. 3, the temperature buffer device 34 is a water storage tank 35 for temporarily storing reactor water. The water storage tank 35 has an inlet nozzle 36 on one side and an outlet nozzle 37 on the other side, and is arranged so that the inlet nozzle 36 has a head at a distance from the outlet nozzle 37. Originally, low-temperature reactor water is stored in the water storage tank 35. Even if high-temperature reactor water flows in from the inlet nozzle 36 momentarily, high-temperature reactor water and low-temperature reactor water are stored in the water storage tank 35. Is mixed, the temperature of the reactor water flowing out of the outlet nozzle 37 can be lowered.

Therefore, in the present embodiment, when the reactor water whose temperature has fallen is cooled by the non-regenerative heat exchanger 28, the reactor water is cooled with a smaller amount of cooling water than before, and the heat applied to the reactor pressure vessel 21 is reduced. The impact can be suppressed to a low level, and environmental problems due to the hot water drainage of the cooling water accompanying the cooling of the reactor water can be reduced.

FIG. 4 is a schematic diagram showing a second example of the temperature buffer device according to the present embodiment. The same parts as those of the temperature buffer device according to the first embodiment are denoted by the same reference numerals.

The temperature buffer device 34 according to the present embodiment is a water storage tank 35 for temporarily storing reactor water. The water storage tank 35 is provided with an inlet nozzle 36 and an outlet nozzle 37, and the free surface 38 of the reactor water in the tank. Is formed with an air layer 39.

In this embodiment, since the high-temperature reactor water is cooled by the gas layer 39, the temperature drop can be made relatively quicker than cooling the high-temperature reactor water with the low-temperature reactor water left beforehand. It is.

FIG. 5 is a schematic view showing a third example of the temperature buffer according to the present embodiment. The same parts as those of the temperature buffer device according to the first embodiment are denoted by the same reference numerals.

In this embodiment, a pressurizer 40 is provided in a water storage tank 35, and a pressing force is applied to a free surface 38 of the reactor water by a medium supplied from the pressurizer 40, for example, an inert gas such as air or nitrogen. The layer 39 is ensured.

Therefore, in this embodiment, since the gas layer 39 of the water storage tank 35 is ensured by the medium of the pressurizer 40, the high-temperature reactor water supplied from the inlet nozzle 36 can be cooled relatively quickly. .

FIG. 6 is a schematic view showing a fourth example of the temperature buffer according to the present embodiment. The same parts as those of the temperature buffer device according to the first embodiment are denoted by the same reference numerals.

In this embodiment, the slit 4 is
1 is formed. In this embodiment, the inlet nozzle 36
Since the slit 41 is formed in the air layer 39,
In this case, even if the high-temperature reactor water cannot be cooled, even if thermal strain occurs in the inlet nozzle 36, it can be absorbed by the slit 41, and the material strength of the inlet nozzle 36 can be maintained in a high state. .

FIG. 7 is a schematic system diagram showing a third embodiment of the RHR system according to the present invention. The same parts as those of the first embodiment are denoted by the same reference numerals.

In the present embodiment, another non-regenerative heat exchanger 42 is provided between the recirculation pump 22 of the reactor recirculation system 23 and the RHR pump 26 of the RHR system 20. And a non-regenerative heat exchanger bypass system 44 having a bypass valve 43.

When the reactor water flows into the RHR system 20 when the operation of the reactor pressure vessel 21 is stopped, the RHR system 2
Each device of the reactor water cooling system 29 and the bypass system 32 of 0 may be damaged. For this reason, in this embodiment, the reactor water is pre-cooled by the non-regenerative heat exchanger 42 to protect each device of the RHR system 20 from thermal shock, and the temperature of the reactor water and the temperature of the metal of each device are substantially the same. When this happens, the bypass valve 43 is opened, and the reactor water as the cooling water from the cooling water return system 33 is supplied to the reactor pressure vessel 21 via the non-regenerative heat exchanger bypass system 44 and the reactor recirculation system 23. Back to.

As described above, in this embodiment, the non-regenerative heat exchanger 42 is provided between the recirculation pump 22 of the reactor recirculation system 23 and the RHR pump 26 of the RHR system 20 to cool the reactor water in advance. Since the power is supplied to each device of the RHR system 20 after that, each device can be reliably protected from the thermal shock of the high-temperature reactor water.

FIG. 8 is a schematic system diagram showing a fourth embodiment of the RHR system according to the present invention. The same parts as those of the first embodiment are denoted by the same reference numerals.

In this embodiment, a non-regenerative heat exchanger 42 is provided between the recirculation pump 22 of the reactor recirculation system 23 and the RHR pump 26 of the RHR system 20.
Non-regenerative heat exchanger bypass system 4 with bypass valve 43
4, while an inverter circuit 46 is incorporated in a motor 45 for driving the RHR pump 26.

In the present embodiment, since the recirculation pump 22 is operated continuously, unlike the conventional case, the inverter circuit 46 is incorporated in the motor 45 for driving the RHR pump 26. Effective driving with less consumption can be performed.

FIG. 9 is a schematic system diagram showing a fifth embodiment of the RHR system according to the present invention. The same parts as those of the first embodiment are denoted by the same reference numerals.

In the present embodiment, the flow control valve 4 for the head spray system is provided at the outlet side of the non-regenerative heat exchanger 28 of the reactor water cooling system 29.
7 and a flow rate adjusting valve 48 for a reactor recirculation system in the cooling water return system 33.

In this embodiment, a flow control valve 47 for the head spray system is provided on the outlet side of the non-regenerative heat exchanger 28 of the reactor water cooling system 29, and the flow rate for the reactor recirculation system is provided in the cooling water return system 33. A regulating valve 48 is provided, and each flow regulating valve 47, 4
Since the flow rate of the reactor water as the cooling water was controlled in step 8 to return the reactor water to the reactor pressure vessel 21, an appropriate amount of reactor water could be returned to the reactor pressure vessel 21 and the reactor water was subjected to thermal shock due to thermal shock. The furnace pressure vessel 21 can be protected.

FIG. 10 is a schematic system diagram showing a sixth embodiment of the RHR system according to the present invention. The same parts as those of the first embodiment are denoted by the same reference numerals.

In this embodiment, the reactor water cooling system 29 is connected to the reactor recirculation system 23, the bypass system 32 is connected to the head spray system 25, and the reactor water cooling system 29 and the bypass system 32 are separately provided. It is designed for exclusive use so that it can be used independently.

The reactor water cooling system 29 includes a first sub-bypass system 50 in which a bypass valve 49 is interposed in addition to the flow control valve 27 and the non-regenerative heat exchanger 28.

The bypass system 32 includes a non-regenerative heat exchanger 51 and a flow control valve 52 and a bypass valve 5.
3 and a second sub-bypass system 54.

In this embodiment, when the operation of the reactor pressure vessel 21 is stopped, the reactor recirculation system 23
The reactor water taken in through the recirculation pump 22 is cooled in the reactor water cooling system 29, and the reactor water as the cooling water is cooled through the reactor water return system 33 and the reactor recirculation system 23. When returning to the vessel 21, even if an accident should occur due to an unexpected situation, the reactor water can be returned to the reactor pressure vessel 21 via the head spray system 25 using the second sub-bypass system 54. .

Therefore, according to the present embodiment, since the reactor water cooling system 29 and the bypass system 32 are dedicated so that they can be used separately and independently, the reactor water is surely returned to the reactor pressure vessel 21. Therefore, thermal stress generated in the reactor pressure vessel 21 can be suppressed low.

FIG. 11 is a schematic system diagram showing a seventh embodiment of the RHR system according to the present invention. The same parts as those of the first embodiment are denoted by the same reference numerals.

In this embodiment, a temperature buffer 34 is provided between the recirculation pump 22 of the reactor recirculation system 23 and the RHR pump 26 of the RHR system 20, and the cooling water return system 33 is connected to the temperature buffer 34. Connected to.

The temperature buffer device 34 is connected to the reactor recirculation system 23.
A circulation inlet nozzle 56 connected to the cooling water return system 33 with a flow control valve 55 interposed therebetween.
The water storage tank 35 has an outlet nozzle 37 connected to the RHR pump 26 of the RHR system 20.

As described above, in the present embodiment, the temperature buffer device 34 is provided between the recirculation pump 22 and the RHR pump 26, and the cooling water return system 33 is connected to the temperature buffer device 34 so that the reactor Reactor pressure vessel 2 via circulation system 23
1 to the high-temperature reactor water supplied to the temperature buffer 34, the reactor water as the cooling water supplied from the cooling water return system 33 to the temperature buffer 34 is brought to an appropriate temperature, and the combined water is supplied to the RHR system. As a result, the thermal shock received from the reactor water of each device of the RHR system 20 can be kept low, and the material strength can be kept high.

FIG. 12 is a schematic system diagram showing an eighth embodiment of the RHR system according to the present invention. The same parts as those of the first embodiment are denoted by the same reference numerals.

In this embodiment, a regenerative heat exchanger 57 is provided between the recirculation pump 22 of the reactor recirculation system 23 and the RHR pump 26 of the RHR system 20, and the regenerative heat exchanger 57 is provided with a flow control valve. The cooling water return system 33 provided with the reactor pressure vessel 58 is connected to the reactor pressure vessel 2 via the reactor recirculation system 23.
This is obtained by exchanging heat with the high-temperature reactor water supplied to the regenerative heat exchanger 57 from the reactor water as cooling water supplied to the regenerative heat exchanger 57 from the cooling water return system 33.

As described above, in the present embodiment, the reactor water as the cooling water supplied from the flow regulating valve 58 through the cooling water return system 33 is supplied to the reactor water of the reactor pressure vessel 21. Since the heat exchange was performed at 57, the reactor water supplied to the RHR system 20 was supercooled by the non-regenerative heat exchanger 28 and returned to the cooling reactor water return system 33. It can be heated to the appropriate temperature by heating with furnace water.

Therefore, according to this embodiment, the reactor water as the cooling water supplied from the regenerative heat exchanger 57 to the reactor pressure vessel 21 via the head spray system 25 is kept at an appropriate temperature. The thermal shock received from the reactor water in the container 21 can be reduced, and the generation of thermal stress due to the reactor water can be suppressed.

[0069]

As described above, the apparatus for removing residual heat according to the present invention allows the recirculation pump of the reactor recirculation system to perform continuous operation and cools by the non-regenerative heat exchanger of the reactor water cooling system. A means to join the high-temperature reactor water from the bypass system to the reactor water, and the combined water was adjusted to an appropriate temperature and returned to the reactor pressure vessel. Can be suppressed, and an unexpected electrical accident or the like that occurs with the intermittent operation of the recirculation pump as in the related art can be prevented, and stable operation can be performed.

In the residual heat removing apparatus according to the present invention, cooling means is provided between the recirculation pump of the reactor recirculation system and the pump of the residual heat removing apparatus, and the cooling means removes water from the reactor pressure vessel. Since the high-temperature reactor water is supplied to the reactor water cooling system at an appropriate temperature, the generation of thermal stress from the reactor water of each component of the reactor water cooling system can be reduced, and stable material strength can be maintained. it can.

[Brief description of the drawings]

FIG. 1 is a schematic system diagram showing a first embodiment of a residual heat removing device according to the present invention.

FIG. 2 is a schematic system diagram showing a second embodiment of the residual heat removing device according to the present invention.

FIG. 3 is a schematic view showing a first example of the second embodiment of the residual heat removing device according to the present invention.

FIG. 4 is a schematic diagram showing a second example of the second embodiment of the residual heat removing device according to the present invention.

FIG. 5 is a schematic diagram showing a third example of the second embodiment of the residual heat removing device according to the present invention.

FIG. 6 is a schematic view showing a fourth example of the second embodiment of the residual heat removing apparatus according to the present invention.

FIG. 7 is a schematic system diagram showing a third embodiment of the residual heat removing device according to the present invention.

FIG. 8 is a schematic system diagram showing a fourth embodiment of the residual heat removing device according to the present invention.

FIG. 9 is a schematic system diagram showing a fifth embodiment of the residual heat removing device according to the present invention.

FIG. 10 is a schematic system diagram showing a sixth embodiment of the residual heat removing device according to the present invention.

FIG. 11 is a schematic system diagram showing a seventh embodiment of the residual heat removing device according to the present invention.

FIG. 12 is a schematic system diagram showing an eighth embodiment of the residual heat removing device according to the present invention.

FIG. 13 is a schematic system diagram showing a conventional residual heat removing device.

[Explanation of symbols]

 DESCRIPTION OF SYMBOLS 1 Residual heat removal apparatus (RHR system) 2 Head spray system 3 Reactor recirculation system 4 Reactor pressure vessel 5 Non-regenerative heat exchanger 6 RHR pump 7 Recirculation pump 8 Bypass valve 9 and 10 Flow control valve 11 Reactor water cooling System 12 Bypass system 13 Cooling reactor water return system 20 Residual heat removal device (RHR system) 21 Reactor pressure vessel 22 Recirculation pump 23 Reactor recirculation system 24 Flow control valve 25 Head spray system 26 RHR pump 27 Flow control valve 28 Non-regenerative heat exchanger 29 Furnace water cooling system 30 Bypass valve 31 Check valve 32 Bypass system 33 Cooling furnace water return system 34 Temperature buffer device 35 Water tank 36 Inlet nozzle 37 Outlet nozzle 38 Free surface 39 Gas layer 40 Pressurizer 41 Slit 42 Non-regenerative heat exchanger 43 Bypass valve 44 Non-regenerative heat exchanger bypass system 45 Motor 46 Inverter cycle 47 Flow control valve for head spray system 48 Flow control valve for reactor recirculation system 49 Bypass valve 50 First sub bypass system 51 Non-regenerative heat exchanger 52 Flow control valve 53 Bypass valve 54 Second sub bypass valve 55 Flow control valve 56 Recirculation inlet nozzle 57 Regeneration heat exchanger

 ──────────────────────────────────────────────────続 き Continuing from the front page (72) Inventor Masayuki Asano 2--4, Suehirocho, Tsurumi-ku, Yokohama-shi, Kanagawa Prefecture Inside the Toshiba Keihin Plant (72) Inventor Yuji Saito 2-chome, Suehirocho, Tsurumi-ku, Yokohama-shi, Kanagawa Address: Toshiba Keihin Plant (72) Inventor Kengo Wakamatsu 1 Toshiba-cho, Fuchu-shi, Tokyo Toshiba Corporation Fuchu Plant (72) Inventor Ning Kanazawa 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Toshiba Yokohama Co., Ltd. In-house (72) Inventor Ayaichi Saeki 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa In-house Yokohama Toshiba Corporation

Claims (14)

[Claims] 1. A reactor system comprising: a bypass system juxtaposed to a reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system; In the residual heat removing device for returning one of the system reactor water to the reactor pressure vessel, a part of the bypass system reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining part of the bypass system is removed. A cooling water return system for combining the reactor water with the reactor water cooled by the reactor water cooling system and returning the reactor water to the reactor pressure vessel. 2. A reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system, the reactor water cooling system comprising a bypass system, and a reactor water cooled by the reactor water cooling system and a bypass system. In the residual heat removing device for returning one of the system reactor water to the reactor pressure vessel, a part of the bypass system reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining part of the bypass system is removed. The reactor water is cooled by the reactor water cooling system, the reactor water is cooled, and the reactor water is returned to the reactor pressure vessel.The cooling water return system, and the temperature provided between the reactor recirculation and the reactor water system A residual heat removing device comprising a buffer device. 3. The residual heat removing device according to claim 2, wherein the temperature buffer device is a water storage tank. 4. The residual heat removing device according to claim 3, wherein the water storage tank has an inlet nozzle and an outlet nozzle, and the water tank is installed with a head formed at a distance from the inlet nozzle and the outlet nozzle. . 5. The residual heat removing device according to claim 3, wherein the water storage tank has a gas layer formed on a free surface of the reactor water. 6. The residual heat removing device according to claim 3, wherein the water storage tank is provided with a pressurizer. 7. The residual heat removing device according to claim 4, wherein a slit is formed in an inlet nozzle of the water storage tank. 8. A reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system, the reactor water cooling system being provided in parallel with the reactor water cooled by the reactor water cooling system and the bypass. In the residual heat removing device for returning one of the system reactor water to the reactor pressure vessel, a part of the bypass system reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining part of the bypass system is removed. A cooling water return system that combines the reactor water with the reactor water cooled by the reactor water cooling system and returns the reactor water to the reactor pressure vessel; and a non-regeneration system provided between the reactor recirculation and the cooling water system. A residual heat removing device comprising a heat exchanger. 9. The apparatus according to claim 8, wherein the non-regenerative heat exchanger includes a non-regenerative heat exchanger bypass system. 10. A reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system, the reactor water cooling system having a bypass system, and the reactor water cooled by the reactor water cooling system and the bypass system. In the residual heat removing device for returning one of the system reactor water to the reactor pressure vessel, a part of the bypass system reactor water is returned to the reactor pressure vessel via the head spray system, and the remaining part of the bypass system is removed. A non-regenerative heat exchange between the reactor water recirculation system and the reactor water recirculation system, in which the reactor water is combined with the reactor water cooled by the reactor water cooling system and returned to the reactor pressure vessel. And a non-regenerative heat exchanger with a non-regenerative heat exchanger bypass system.
A residual heat removing device, wherein an inverter circuit is incorporated in a motor for driving the residual heat removing pump of the reactor water cooling system. 11. A reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system, a bypass system provided in parallel with the reactor water cooling system, and a reactor water cooled by the reactor water cooling system and a bypass system. In the residual heat removing device that returns one of the system reactor water to the reactor pressure vessel, the reactor water of the bypass system is returned to the reactor pressure vessel via the head spray system, and is cooled by the reactor water cooling system. Flow rate control valve for supplying the reactor water to the head spray system by controlling the flow rate,
A residual heat removing device, comprising: a flow rate control valve for controlling a flow rate of the reactor water cooled by the reactor water cooling system and returning the reactor water from the cooling reactor water return system to the reactor pressure vessel. 12. A reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system, the reactor water cooling system comprising a bypass system, and a reactor water cooled by the reactor water cooling system. In the residual heat removing device for returning one of the system reactor water to the reactor pressure vessel, the reactor water cooling system is provided with a first sub-bypass system, and the bypass system is provided with a second sub-bypass system. Characteristic residual heat removal equipment. 13. A reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system, the reactor water cooling system comprising: In the residual heat removing device for returning one of the system reactor water to the reactor pressure vessel, a part of the bypass system reactor water is returned to the reactor pressure vessel via a head spray system, and the remaining part of the bypass system is removed. A cooling water return system that combines the reactor water with the reactor water cooled by the reactor water cooling system and returns to the reactor pressure vessel, and a temperature buffer between the reactor recirculation and the cooling water system. Wherein the cooling water return system is connected to the temperature buffer device. 14. A reactor water cooling system for cooling reactor water taken from a reactor pressure vessel via a reactor recirculation system, the reactor water cooling system comprising a bypass system, and a reactor water cooled by the reactor water cooling system. In the residual heat removing device for returning one of the system reactor water to the reactor pressure vessel, a regenerative heat exchanger is provided between the reactor recirculation system and the reactor water cooling system, and the bypass system furnace is provided. The reactor water cooled by the reactor water cooling system is combined with the reactor water, and part of the combined water is returned to the reactor pressure vessel, while the rest of the combined water is supplied to the regenerative heat exchanger. A residual heat removing device comprising a system.