JP2001074874A - Cooling equipment for nuclear reactor or the like - Google Patents

Abstract

PROBLEM TO BE SOLVED: To continuously perform cooling work in periodical inspection work without any interruption by changing a conventional seawater cooling water system to an alternative cooling water system for removing decay heat generated when a reactor is stopped. SOLUTION: In the removal of decay heat when a reactor is normally stopped, RPV2 is cooled by an RHR pump 5 and an RHRS pump 7 through RHR heat exchangers 48 and 49. A fuel pool 3 is cooled by allowing fuel pool water circulated by an FPC pump 12 to pass through FPC heat exchangers 33 and 34. An RCW cooling load 20 is cooled by allowing cooling water circulated by an RCW pump 15 to pass through an RCW heat exchanger 16 for carrying out cooling using seawater by an SW pump 17. When a heat removal system other than the seawater system is used during inspection for reducing the period of periodical inspection, a switching valve 46 is opened and closed, and the cooling water to the FPC heat exchangers 33 and 34 for substitution is supplied by the cooling water where an air-cooling-type refrigerator 31 for substitution is used, thus the heat exchanger is cooled.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention removes decay heat of a reactor core, decay heat in a spent fuel pool, and other equipment generated when a reactor is shut down in a boiling water nuclear power plant. For cooling equipment such as nuclear reactors.

[0002]

2. Description of the Related Art A conventional cooling equipment for a nuclear reactor in a boiling water nuclear power plant when the reactor is stopped will be described with reference to FIG. When the reactor is shut down, decay heat is generated from the fuel in a reactor pressure vessel (hereinafter referred to as RPV) 2 installed in the reactor well 1, but the decay heat is taken away by the cooling water in the RPV 2, and together with the cooling water The residual heat removal system pump (hereinafter, referred to as RHR pump) 5 connected to the RPV 2 and the residual heat removal system heat exchanger (hereinafter, referred to as RHR heat exchanger) 6 are supplied through a supply line and cooled. It is returned to RPV2 again.

[0003] Here, seawater from a residual heat removal system seawater pump (hereinafter referred to as RHRS pump) 7 flows into the RHR heat exchanger 6, cools the inside of the RHR heat exchanger 6, and heats the seawater. Finally heat is removed (cooled) to the sea. A plurality of heat removal cooling systems by the RHR heat exchanger 6 and the RHRS pump 7 are installed in parallel.

[0004] Decay heat generated from spent fuel stored in a spent reactor fuel pool (hereinafter referred to as a fuel pool) 3 is taken away by the pool water in the fuel pool 3, and the heated pool water is removed. From the skimmer surge tank 4 through a fuel pool cooling / purifying system pump (hereinafter, referred to as FPC pump) 12, a fuel pool cooling / purifying system filtration and desalination device (hereinafter, FPC)
After flowing into a fuel pool cooling and purifying system heat exchanger (hereinafter referred to as an FPC heat exchanger) 13, the fuel is cooled through a return line 13 and returned into the fuel pool 3 again. ing.

[0005] Here, a plurality of heat removal (cooling) systems from the FPC heat exchanger 13 are installed in parallel, and circulation of cooling water by a reactor auxiliary equipment cooling water pump (hereinafter referred to as RCW pump) 15. Auxiliary cooling system heat exchanger (hereinafter RC)
The heat is finally removed (cooled) to the sea by a regular seawater pump 17 through a W heat exchanger 16).

Further, a cooling water system (hereinafter referred to as RC)
W), or the cooling loads 27 and 28 of the turbine accessory cooling water system (hereinafter referred to as TCW), respectively, by circulating the cooling water by the RCW pump 15 or the TCW pump 18, respectively. Or TCW heat exchanger 19
The heat is finally removed (cooled) to the sea by the regular seawater pump 17 after passing through.

In the event that the reactor coolant is lost when the reactor is shut down, the design is such that the emergency core cooling system can maintain the core flooding. RHRS for system auxiliary equipment cooling load (ECCS load) 24
Seawater flows in from the pump 7 and cools, and finally heat is removed (cooled) to the sea and discharged to the sea.

Here, the RHRS pump 7 for pumping seawater as a conventional emergency equipment takes water from a separate water intake tank for each system from the viewpoint of multiplexing, and a plurality of regular seawater pumps 17 are also installed. Water is taken from a separate water tank near the water pump. Furthermore, some plants have only one seawater cooling system discharge pipe in the end, and some plants do not directly cool seawater for heat removal and emergency equipment. Heat is removed by seawater and finally released to the sea for heat removal (cooling)
It is carried out.

[0009]

At present, all the heat removal (cooling) systems are designed to ultimately collect seawater from the sea through a seawater cooling system and discharge heated seawater to the sea. Although there is no particular problem in the operation of the heat removal system when the reactor is shut down, there are problems in the following two points.

The first point is that the seawater cooling system, which is a normal heat removing means, cannot be inspected during normal operation, so that the inspection is performed at the time of reactor shutdown, and a certain inspection period is required. . Considering the direction of shortening the period of periodic inspection (hereinafter referred to as regular inspection), it is necessary to inspect all intake tanks as soon as possible after reactor shutdown.

However, in this case, it is necessary to continuously carry out the heat removal of the decay heat in the RPV 2 or the fuel pool 3 and other equipment requiring heat removal through regular inspection. In addition, since the shortening of the regular inspection shortens the pool gate closing time from the viewpoint of cooling the fuel pool, it also has a severe direction in heat removal of the spent fuel pool cooling and purification system.

The second point is that some plants share part of the seawater cooling system piping, and depending on the location of the piping inspection, during the inspection period, the removal of decay heat in the RPV 2 or the fuel pool 3 is performed. Becomes difficult.

SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problem, and is an alternative to the conventional seawater cooling system for cooling decay heat of a RPV or a fuel pool generated at the time of a reactor shutdown during regular inspection. Provide cooling equipment such as a nuclear reactor, which can provide continuous cooling during regular inspection by providing a cooling water system and reduce inspection and use of the seawater cooling system to shorten regular inspection. The purpose is to:

[0014]

According to the first aspect of the present invention, there is provided a cooling system for a nuclear reactor or the like for cooling core collapse heat generated when a reactor is shut down or heat generated from equipment. Normally installed in at least one system selected from reactor coolant purification system, reactor accessory cooling system, fuel pool cooling purification system, residual heat removal system, reactor isolation cooling system, or turbine accessory cooling system It is characterized by connecting an alternative cooling water system or gas cooling system in addition to the cooling water system at the time.

According to a second aspect of the present invention, the normal cooling water system and the alternative cooling water system are connected to a secondary cooling water pipe of the residual heat removing system heat exchanger of the residual heat removing system, and the reactor is stopped. The piping is connected so that the core collapse heat at the time can be removed by any of the cooling water systems.

According to a third aspect of the present invention, the normal cooling water system and the alternative cooling water system are connected to a secondary cooling water pipe of a reactor coolant purification system non-regenerative heat exchanger of the reactor coolant purification system. ,
The reactor coolant purification system regenerative heat exchanger of the reactor coolant purification system is a one-sided non-flow operation, and the core decay heat at the time of the reactor shutdown together with the residual heat removal system heat exchanger is used for the reactor cooling. It is characterized in that it is connected to a pipe so as to be removed by a material purification system non-regenerative heat exchanger.

According to a fourth aspect of the present invention, a cooling water system alternative to the residual heat removal system and the reactor coolant purifying system is a seawater system using a seawater pump exclusively used when the reactor is stopped.

According to a fifth aspect of the present invention, the alternative cooling water system for the residual heat removal system and the reactor coolant purification system is a gas cooling system using an air cooler or a refrigerator using the atmosphere as a cooling source. Features.

The invention according to claim 6 is characterized in that piping is connected so as to remove core decay heat generated when the reactor is stopped and to remove heat generated in the spent fuel pool when the reactor is stopped. I do.

According to a seventh aspect of the present invention, a secondary cooling water pipe is connected to a heat exchanger of the system with respect to a cooling load of each of the systems requiring cooling when the reactor is stopped. The cooling water piping is connected to the normal cooling water system and an alternative cooling water system, and piping is connected so that a load requiring heat removal when the reactor is stopped is removed by an alternative cooling water system other than the normal cooling water system. It is characterized by becoming.

The invention of claim 8 is characterized in that when the reactor is stopped, the secondary cooling water pipe is provided with an alternative cooling water system in place of the normal cooling water system with respect to the cooling load of the auxiliary equipment of the emergency core cooling system. It is characterized in that the pipes are connected so that the reactor core flooding can be maintained when the reactor coolant is lost when the reactor is stopped.

According to a ninth aspect of the present invention, the normal-time cooling water system and the alternative cooling water system are connected to the secondary-side cooling water pipe with respect to a cooling load of the emergency power generation facility when the reactor is stopped. It is characterized in that piping is connected so that cooling can be continued when external power is lost during shutdown.

According to a tenth aspect of the present invention, there is provided at least one cooling facility selected from the second to fifth aspects, and a sixth aspect of the present invention.
A plurality of at least one cooling facility selected from the group consisting of

[0024] The invention according to claim 11 is that the cooling water system at the normal time and the alternative cooling water system are connected to a secondary cooling water pipe of a fuel pool cooling and purifying system heat exchanger of the fuel pool cooling and purifying system,
A piping is connected so that decay heat generated in the fuel pool when the reactor is stopped is removed by the alternative cooling water system other than the normal cooling water system.

A twelfth aspect of the present invention is characterized in that a pipe that bypasses the filtration and desalination device of the fuel pool cooling and purifying system is operated. According to a thirteenth aspect of the present invention, a first heat exchanger and a pump are provided in a fuel pool cooling and purifying system for purifying pool water of a fuel pool, and a second heat exchanger and a pump connected to the fuel pool are provided. A cooling water system is connected to a secondary cooling water pipe of the second heat exchanger, and the decay heat generated in the fuel pool when the reactor is stopped is transferred to the second heat exchanger in addition to the first heat exchanger. It is characterized by being connected by piping so as to be removed by a heat exchanger.

According to a fourteenth aspect of the present invention, a normal cooling water system and an alternative cooling water system are connected to the fuel pool cooling and purification system, and the alternative cooling water system is a seawater system using a seawater pump when the reactor is stopped. Features.

According to a fifteenth aspect of the present invention, the normal cooling water system and the alternative cooling water system connected to the fuel pool cooling and purifying system are an air cooler using an air as a cooling source or a gas cooling system using a refrigerator. It is characterized by.

[0028] The invention according to claim 16 is characterized in that the first heat exchanger or the second heat exchanger is collapsed so as to remove the core collapse heat at the time of reactor shutdown in addition to the heat generated in the fuel pool. It is characterized by being connected to a heat removal system by piping.

The invention according to claim 17 is characterized in that the piping is connected so that the core decay heat when the reactor is shut down is removed by a non-regenerative heat exchanger of a reactor coolant purification system. The invention of claim 18 is characterized in that the alternative cooling water system of the reactor coolant purifying system comprises the alternative cooling water system of claim 14 or 15.

According to a nineteenth aspect of the present invention, an alternative cooling water system is connected to a secondary cooling water pipe for a cooling load that requires cooling when the reactor is stopped, and the heat generated when the reactor is stopped is transferred to the normal cooling water system. It is characterized by being connected to a pipe so as to be removed by an alternative cooling water system other than the cooling water system at the time.

[0031] The invention of claim 20 is that, even when the reactor is shut down, the cooling water piping for the normal time and the alternative cooling water system are connected to the secondary cooling water piping for the cooling load of the auxiliary equipment of the emergency core cooling system. It is characterized by being connected.

The invention of claim 21 is characterized in that, when the reactor is shut down, a cooling water system for normal use and an alternative cooling water system are connected to the secondary cooling water pipe for the cooling load of the emergency power generation equipment, and the reactor is stopped. In this case, the piping is connected so that the cooling can be continued by the alternative cooling water system when the external power supply is lost.

According to a twenty-second aspect of the present invention, at least one cooling facility selected from the eleventh to fifteenth aspects is provided,
, A plurality of at least one cooling equipment selected from the group consisting of a plurality of cooling water systems selected from the group consisting of a plurality of cooling water systems, and a pipe connection so that the alternative cooling water system is shared between the respective systems.

According to the first aspect of the present invention, in the case where heat must be removed instead of decay heat when the reactor is shut down by the normal cooling water system using seawater, an alternative is to be provided as a standby during regular inspection. By using the cooling water system, heat removal of decay heat or other equipment requiring heat removal can be performed, thereby shortening the regular inspection.

Next, according to the invention corresponding to the second to tenth aspects, in the case where heat removal must be performed in place of normal heat removal by the cooling water system using seawater due to shortened regular inspection, etc. Equipment that requires decay heat in the RPV, furthermore, decay heat in the fuel pool or other heat removal by using an alternative heat removal path different from the normal heat removal path using an RHR heat exchanger or the like Can be removed.

In the second aspect, the RP is formed by using an RHR heat exchanger.
The facility capable of removing the decay heat in the V is provided in claim 3 by using a non-regenerative heat exchanger for purifying the reactor coolant, together with the RHR heat exchanger of claim 2, and The heat removal capacity of the system can be further improved by using equipment capable of removing decay heat and also performing F / D bypass operation of the reactor coolant purification system.

Further, in the fourth and fifth embodiments, the seawater system, the air-cooled air cooler, and the air-cooled refrigerator are used as the alternative cooling water system in the order of the second embodiment. The problem can be solved by providing equipment capable of removing the heat of decay heat in the interior.

Next, the equipment capable of removing the heat of the fuel pool in addition to the decay heat in the RPV according to the sixth aspect will be sequentially described as the equipment for cooling the decay heat other than the decay heat according to the first to seventh aspects. The problem can be solved by removing the heat of the equipment that needs the heat removal of the normal system, the auxiliary equipment of the emergency core cooling system, and the emergency power generation equipment.

Claim 10 is a combination of the heat removal equipment of Claims 2 to 9 as required and enables necessary decay heat or heat removal of equipment. It is possible to solve the problem of removing heat during regular inspection using a heat system.

According to the eleventh to twenty-second aspects of the present invention, when it is necessary to perform heat removal instead of normal heat removal by the cooling water system using seawater due to shortened regular inspection, etc., a conventional FPC heat exchanger or the like is used. Using the alternative heat removal path different from the normal heat removal path to remove heat from the decay heat in the fuel pool, and further from decay heat in the RPV or other equipment that requires heat removal. Can be.

In the eleventh aspect of the present invention, a facility capable of removing the decay heat in the fuel pool using the FPC heat exchanger is provided. The purification system is operated by also performing the F / D bypass operation, thereby improving the heat removal capacity of the system. The invention of claim 13 further includes a heat exchanger in addition to the invention of claim 11 or 12. Alternatively, it is possible to solve the problem by providing a facility capable of removing decay heat in the fuel pool by adding a pump.

According to the fourteenth and fifteenth aspects, from the eleventh aspect,
The alternative cooling water system described in the invention of the thirteenth invention shall be a seawater system, an air-cooled air cooler, and an air-cooled refrigerator in order to provide facilities that can remove decay heat in the fuel pool for each. Thus, the problem can be solved.

According to the invention of claim 16, there is provided a facility capable of removing heat of RPV in addition to the decay heat in the fuel pool.
In the invention of claim 16, in addition to the invention of claim 16, equipment capable of removing the heat of the RPV by using the non-regenerative heat of the reactor coolant purification system is provided. The problem can be solved by providing a facility in which the heat removal capability of the system is further improved by performing the operation.

According to the eighteenth aspect of the invention, the problem can be solved by specifically showing a cooling water system which is an alternative to the non-regenerative heat exchanger for purifying the reactor coolant. Claims 19 to 21
In the invention of the present invention, by removing heat from equipment that requires regular heat removal in order as a function of cooling in addition to the decay heat described in the invention of claim 1, auxiliary equipment for emergency core cooling system, and emergency power generation equipment Problems can be solved.

According to the invention of claim 22, the heat removal equipment of the inventions of claims 11 to 21 can be arbitrarily combined as necessary to remove the necessary decay heat or heat of the equipment. It is possible to solve the problem of removing heat during the regular inspection using a heat removal system other than the system. In addition, the reliability can be further improved by giving redundancy to the alternative heat removal system, and the alternative cooling system can be shared between plants.

[0046]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS (First Invention) A first embodiment of a cooling facility such as a nuclear reactor according to the present invention will be described with reference to FIG. FIG. 1 is an apparatus and piping system diagram according to the present embodiment. In FIG. 1, the same parts as those in FIG. This embodiment is different from the conventional example in that the first and second alternative FPC heat exchangers are provided in the spent fuel pool cooling and purification system corresponding to the FPC heat exchanger 13 of the conventional example.
33, 34 are installed, and the first alternative air-cooled refrigerator 31 is connected to the cooling water piping 37 on the secondary cooling water piping 35 of these heat exchangers 33, 34.
And a replacement pump 39 and a plurality of switching valves 46 are provided in a pipe between the first replacement air-cooled refrigerator 31 and the first replacement FPC heat exchanger 33.

Also, a cooling water pipe 37 from the first air-cooled refrigerator 31 is connected to a secondary cooling water pipe 36 of the second alternative FPC heat exchanger 34, and a switching valve 46 is installed. It is in. RC
W heat exchanger 16 and first and second FPC heat exchangers 33 and 34
An RCW cooling load 20 that requires cooling at the time of regular inspection and an RCW cooling load 21 that does not require cooling at the time of regular inspection are connected vertically.

Next, the operation will be described. RPV pump 5 and RHR pump 5 are used to remove decay heat during normal reactor shutdown.
First or second RHR heat exchanger by HRS pump 7
Perform through 48 or 49. The fuel pool 3 is cooled by the fuel pool water circulated by the FPC pump 12 by the first and second FPCs.
It is performed through the heat exchangers 33 and 34. The cooling of the RCW cooling load 20 which requires the cooling at the time of the regular inspection of the RCW is performed by cooling the cooling water of the reactor auxiliary equipment circulated by the RCW pump 15 through the RCW heat exchanger 16.
Cooling by seawater is performed by the W pump 17.

On the other hand, when performing heat removal using a heat removal system other than the normal seawater system during regular inspection due to shortened regular inspection, etc.
By opening and closing the switching valve 46, the cooling water to the first and second alternative FPC heat exchangers 33 and 34 is performed by the cooling water using the first alternative air-cooled refrigerator 31. Cooling of the heat exchanger can be performed.

Here, as the first and second alternative FPC heat exchangers 33 and 34, those having a heat removal capacity greater than the heat load required by the normal FPC are installed, and the cooled fuel pool water is used. Is returned to the reactor well 1 so that the decay heat in the RPV 2 can be cooled in addition to the cooling of the fuel pool 3, and the FPC-F / D14 is connected to the F / D bypass pipe.
45, By performing bypass operation using the switching valve 46,
The system flow rate of the system increases, and the heat removal capability can be improved.

According to the present embodiment, in addition to the normal cooling water system using seawater, an alternative cooling water system, that is, an alternative heat exchanger, an alternative pump, and an alternative air-cooled refrigerator are provided, so that the fuel pool is provided. It is possible to obtain a cooling facility such as a nuclear reactor in which the heat removal in the reactor 3 and the RPV 2 can be continuously cooled for most of the period during the regular inspection.

(Second Embodiment) A second embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
In FIG. 2, the description of the parts overlapping with FIGS. 1 and 13 is omitted.

This embodiment is different from the first embodiment in that the cooling water pipe 41 of the CUW CUW non-regenerative heat exchanger 11 is cooled by the cooling air from the first alternative air-cooled refrigerator 31. Water plumbing
37, and a replacement pump 39 and a switching valve 46 are installed in a pipe between the first replacement air-cooled refrigerator 31 and the non-regenerative heat exchanger 11. A CUW regenerative heat exchanger bypass pipe 47 is installed on the outflow side of the CUW regenerative heat exchanger 9 connected to the RPV 2, a switching valve 46 is installed in the bypass pipe 47, and the CUW pump 8 is connected on the inflow side. It is in.

Next, the operation will be described. RPV pump 5 and RHR are used for cooling of RPV 2 for removing heat during normal reactor shutdown.
The first or second RHR heat exchanger 48 by the S pump 7 or
Going through 49. On the other hand, when performing heat removal using a heat removal system other than the normal seawater system during regular inspection due to shortened regular inspection, etc., the switching valve 46 is opened and closed to allow the CUW regenerative heat exchanger 9 to pass one side. By performing the water operation and performing the cooling water to the CUW non-regenerative heat exchanger 11 with the cooling water using the first air-cooled refrigerator 31, the RPV 2 can be cooled.

In addition to this, by performing the bypass operation using the bypass pipe 45 and the switching valve 46 in the reactor coolant purification system filtration and desalination apparatus 10, the system flow rate of the system is increased, and the heat removal capability is improved. Become.

According to the present embodiment, by providing an alternative cooling water system connected to the CUW non-regenerative heat exchanger in addition to the normal cooling water system using seawater, the cooling in the RPV using the reactor coolant purification system is also performed. It is possible to obtain cooling equipment such as a nuclear reactor that can be used at the time of regular inspection.

(Third Embodiment) A third embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
3, the same parts as those in FIGS. 1 and 13 are denoted by the same reference numerals, and the description of the duplicated parts will be omitted.

In the present embodiment, a cooling water pipe 37 from the first alternative air-cooled refrigerator 31 is connected to the secondary cooling water pipe 42 of the RCW cooling load 20 that requires cooling at the time of regular inspection of the RCW, A replacement pump 39 and a plurality of switching valves 46 are installed in a pipe between the first replacement air-cooled refrigerator 31 and the RCW cooling load 20. Also TC
The cooling water pipe 37 from the first air-cooled refrigerator 31 is connected to the secondary-side cooling water pipe 43 of the TCW cooling load 22 that requires cooling at the time of regular inspection of W, and the first alternative air-cooled refrigerator 31 And TCW cooling load
A switching valve 46 is installed in the piping with 22.

Next, the operation will be described. Of the heat removal loads of RCW and TCW during normal reactor shutdown, C shown in FIG.
The heat load other than the UW non-regenerative heat exchanger 11 and the FPC heat exchanger 13 that requires heat removal is the cooling water of the reactor auxiliary equipment, which is supplied to the RCW heat exchanger 16.
Pump water or turbine accessory cooling water via TCW
Seawater cooling is performed by the SW pump 17 via the heat exchanger 19.

On the other hand, when performing heat removal using a heat removal system other than the normal seawater system during regular inspection due to shortening of regular inspection, etc.
By opening and closing the switching valve 46, the R that needs cooling at regular inspection
Cooling water to CW cooling load 20 and TCW cooling load 22
The cooling can be performed by using the cooling water using the alternative air-cooled refrigerator 31 and the alternative pump 39.

According to the present embodiment, in addition to the normal cooling water system using seawater, a cooling water system is provided from the first air-cooled refrigerator 31 to the RCW cooling load that requires cooling during the regular inspection. It is possible to obtain a cooling facility such as a reactor capable of continuously cooling the reactor auxiliary equipment cooling water system and the turbine auxiliary equipment cooling water system that require cooling.

(Fourth Embodiment) A fourth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
In this embodiment, the cooling water is supplied to the emergency core cooling system accessories cooling load 24 so that the cooling water can be supplied to the emergency core cooling system accessories cooling load 24 shown in FIGS. 1 and 13 when the reactor is stopped. Piping
37, a first alternative air-cooled refrigerator 31 as an alternative cooling water system is connected to the cooling water pipe 37, and the first alternative air-cooled refrigerator 31 and the emergency core cooling system auxiliary equipment are cooled. That is, the refrigerator inlet pump 39 is installed in the cooling water pipe 37 with the load 24, and the switching valve 46 is installed.

Next, the operation will be described. In the event of a loss of reactor coolant during normal reactor shutdown, at least one emergency core cooling system can supply cooling water. The heat generated from the machine cooling load 24 is cooled by seawater by the RHRS pump 7.

Here, in the event that a loss of the reactor coolant occurs during heat removal using a heat removal system other than the normal seawater system during the regular inspection due to shortened regular inspection, etc. By supplying the cooling water to the cooling load 24 for the auxiliary cooling system for the core cooling system, the coolant can be supplied into the RPV.

According to the present embodiment, in addition to the normal cooling water system using seawater, a cooling water system connected to the auxiliary core cooling system cooling load for the emergency core cooling system is provided to continuously perform cooling during regular inspection. In this case, it is possible to obtain a cooling facility such as a nuclear reactor capable of supplying coolant to the nuclear reactor even when the nuclear reactor coolant in the RPV is lost.

(Fifth Embodiment) A fifth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
In this embodiment, an emergency power generation equipment cooling load 44 corresponding to the emergency core cooling system auxiliary equipment cooling load 24 shown in FIGS.
The first alternative air-cooled refrigerator is connected to the secondary-side cooling water pipe, so that cooling can be continued even when the external power is lost when the reactor is stopped.

That is, as shown in FIG. 5, the cooling water pipe 37 is connected to the emergency power generation equipment cooling load 44, and the first alternative air-cooled refrigerator 31 is connected to the cooling water pipe 37, First alternative air-cooled refrigerator 31 and emergency power plant cooling load 44
Refrigerator inlet side pump 39 is installed in the piping with
Is installed.

Next, the operation will be described. Even in the event of an external power loss due to an earthquake or the like during normal reactor shutdown,
The emergency power generation equipment cooling equipment 44 can continue to remove heat by operating at least one system. At this time, heat generated from the emergency power generation equipment cooling load 44 is discharged by the emergency power generation equipment cooling seawater pump 40. Cool with seawater.

Here, if the external power supply is lost due to an earthquake or the like while performing heat removal using a heat removal system other than the normal seawater system during regular test due to shortening of the regular test, etc. By supplying the cooling water cooled by the alternative cooling water system, that is, the first alternative air-cooled refrigerator 31 to the power generation equipment cooling load 44, the heat removal can be continued.

According to the present embodiment, if cooling is continuously performed during regular inspection using a heat removal system other than the normal seawater system, even if external power loss occurs due to an earthquake or the like. Further, it is possible to obtain a cooling facility such as a nuclear reactor in which the heat removal can be continued by the alternative cooling water system.

(Sixth Embodiment) A sixth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
A second FPC pump 26 and a third FPC heat exchanger 25 in addition to the FPC pump 12 and the first FPC heat exchanger 33 and the second FPC heat exchanger 34 of the fuel pool cooling and purifying system (FPC); A switching valve 46 is attached to each.

FP is provided on the primary side of the third FPC heat exchanger 25.
A third FPC inlet line 56 connected to the C pump 12 and a reactor well return line 57 connected to the reactor well 1 are connected. A cooling water pipe 37 is connected to the secondary side of the third FPC heat exchanger 25, respectively.

Then, the cooling water pipe 37 from the first alternative air-cooled refrigerator 31 is connected to the secondary cooling water pipe 35 of the first and second FPC heat exchangers 33 and 34 of the FPC. The first alternative air-cooled refrigerator 31 and the first and second FPC heat exchangers 33 and 34
A replacement pump 39 and a switching valve 46 are installed in the piping.
A cooling water pipe 37 from the first alternative air-cooled refrigerator 31 is connected as a secondary cooling water pipe of the third FPC heat exchanger 25.

Next, the operation will be described. RPV pump 5 and RHR are used to remove heat during normal reactor shutdown.
The first RHR heat exchanger 48 or the second R
It is performed through the HR heat exchanger 49, and the cooling of the fuel pool 3 is performed by
The fuel pool water circulated by the PC pump 12 is supplied to the first FP
RCW through the C heat exchanger 33 and the second FPC heat exchanger 34
Reactor accessory cooling water circulated by the pump 15 is cooled by seawater by the SW pump 17 via the RCW heat exchanger 16.

On the other hand, when performing heat removal using a heat removal system other than the normal seawater system during regular inspection due to shortened regular inspection, etc., the switching valve is used.
By opening and closing 46, cooling water to the first FPC heat exchanger 33, the second FPC heat exchanger 34, and the third FPC heat exchanger 25 is used by the first alternative air-cooled refrigerator 31. By using the cooling water, cooling of these heat exchangers can be performed.

Here, as the first and second heat exchangers 33 and 34, those having a heat removal capacity higher than the heat load required by the normal FPC will be installed. In addition to the FPC heat exchanger 25, the capacity of the fuel pool 3 and the decay heat in the RPV 2 can be cooled, and a part of the pool water of the cooled fuel pool 3 is returned to the reactor well 1. .

According to the present embodiment, the reactor in which the heat removal in the fuel pool 3 and the RPV 2 can be continuously cooled for most of the period during the regular inspection using the heat removal system other than the seawater system in the normal state. An equal cooling facility can be obtained.

(Seventh Embodiment) This embodiment relates to an FP
As a cooling water system for normal operation of C and an alternative cooling water system, use a seawater pump installed exclusively for reactor shutdown when using a seawater cooling water system, or use an air cooler or refrigerator with air as a cooling source and a gas cooling system. I did it.

Here, the first and second alternative FPC heat exchangers 33 and 34 of the spent fuel pool cooling and purification system, the CUW non-regenerative heat exchanger 11, the RCW cooling load 20 that requires cooling at regular inspection,
The secondary cooling water piping for the TCW cooling load 22, the cooling load 24 for the emergency core cooling system auxiliary equipment, and the cooling load 44 for the emergency power generation equipment that require cooling during regular inspections is not the first alternative air-cooled refrigerator. And an air cooler using the atmosphere as a cooling source or a seawater pump. Here, when installing the seawater pump, the RHRS pump 7 and the regular seawater pump
Water is taken from 17 water tanks.

According to the present embodiment, the cooling is continuously performed during the periodic inspection using a cooling water system using a seawater pump other than the cooling water system using normal seawater or a gas cooling system using the atmosphere as a cooling source. A cooling facility such as a nuclear reactor can be obtained.

(Eighth Embodiment) This embodiment is directed to the first embodiment.
In the sixth to sixth embodiments, it is assumed that each of the equipments has a configuration in which a plurality of equipments are combined, and the alternative pump 39 and the first alternative air-cooled refrigerator 31 are also used. In some cases, instead of the first alternative air-cooled refrigerator 31, a seawater pump and an air cooler using the atmosphere as a cooling source can be used in common as in the seventh embodiment.

Next, the operation will be described. Since the present embodiment is a combination of the first to seventh embodiments, the operation is the same as that of the first to seventh embodiments. By providing all necessary equipment inside, necessary heat removal assumed at the time of regular inspection can be performed.

According to the present embodiment, there is provided a cooling system such as a nuclear reactor which can continuously perform cooling during regular inspection by a heat removal system other than the cooling water system using seawater during normal times, that is, a cooling water system or a gas cooling system. Obtainable.

(Ninth Embodiment) A ninth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
In this embodiment, the first RHR heat exchanger 48 of the residual heat removal system is used.
The cooling water pipe 37 from the first alternative air-cooled refrigerator 31 is connected to the secondary-side cooling water pipe 50 of the first alternative air-cooled refrigerator.
Replacement pump 39 for piping between 31 and first RHR heat exchanger 48
And a switching valve 46 is installed.

Further, the cooling water pipe 37 from the first alternative air-cooled refrigerator 31 is connected to the secondary cooling water pipe 51 of the second RHR heat exchanger 49, and the first alternative air-cooled refrigeration unit 31 is connected. Piping with machine 31
A switching valve 46 is installed at 37. A supply pipe 29 from the fuel pool to the residual heat removal system on the primary side of the second RHR heat exchanger 49;
A return pipe 30 from the residual heat removal system to the RPV is connected.

The cooling water pipe 37 from the first air-cooled refrigerator 31 is connected to the secondary cooling water pipe 41 of the CUW non-regenerative heat exchanger 11, a switching valve 46 is installed, and the CUW regenerative heat exchanger is connected. 9 is provided with a bypass pipe 47 and a switching valve 46.

Next, the operation will be described. The cooling of the decay heat of RPV2 during normal reactor shutdown is performed by the RHR pump 5, RHRS
The first RHR heat exchanger 48 or the second RHR
The cooling of the fuel pool 3 is performed through the HR heat exchanger 49 and the fuel pool water circulated by the FPC pump 12 shown in FIG. 1 is passed through the first alternative FPC heat exchanger 33 and the second alternative FPC heat exchanger 34. Reactor accessory cooling water circulated by the RCW pump 15 is passed through the RCW heat exchanger 16 to cool seawater by the SW pump 17.

On the other hand, in the present embodiment, the switching valve 46 is opened and closed when performing heat removal using a heat removal system other than the normal cooling water system using seawater during regular inspection due to shortening of regular inspection. As a result, the first RHR heat exchanger 48 and the second RHR heat exchanger 4
9. By cooling water to the CUW non-regenerative heat exchanger 11 with cooling water using the first alternative air-cooled refrigerator 31, cooling of these heat exchangers can be performed.

Here, water taken in cooling by the first RHR heat exchanger 48 or the second RHR heat exchanger 49 is taken from the take-out pipe 29 from the fuel pool 3, and after being cooled, it is cooled. By returning from the return pipe 30 to the RPV 3, it is possible to cool the decay heat in the fuel pool 3 in addition to the cooling to the RPV 2.
In addition, in addition to this, a bypass pipe is connected to the CUW-F / D10.
By performing the bypass operation by installing the switch 45 and the switching valve 46, the system flow rate of the system is increased, and the heat removal capability is improved.

According to the present embodiment, a reactor or the like in which the heat removal in the fuel pool and the RPV can be continuously cooled for most of the period during the regular inspection using the heat removal system other than the seawater system in the normal state. Cooling equipment can be obtained.

(Tenth Embodiment) A tenth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
A cooling water pipe 37 from the first alternative air-cooled refrigerator 31 is connected to a secondary cooling water pipe 42 of the RCW cooling load 20 which needs to be cooled at the time of regular inspection of the reactor auxiliary cooling water system. A replacement pump 39 is installed in a cooling water pipe 37 between the replacement air-cooled refrigerator 31 and the RCW cooling load 20 that needs to be cooled during regular inspection, and a switching valve 46 is connected.

The first cooling water pipe 43 of the TCW cooling load 22, which needs to be cooled at the time of regular inspection of the turbine auxiliary cooling water system,
Connecting the cooling water pipe 37 from the alternative air-cooled refrigerator 31
A switching valve 46 is installed in a pipe between the first alternative air-cooled refrigerator 31 and the TCW cooling load 22 requiring cooling.

Next, the operation will be described. Of the heat removal loads of the reactor auxiliary equipment cooling water system and turbine auxiliary equipment cooling water system during normal reactor shutdown, the heat load that requires heat removal other than the CUW non-regenerative heat exchanger 11 and FPC heat exchanger 13 is the atomic load. Furnace auxiliary equipment cooling water R
Cooling of the service pump 17 or turbine accessory cooling water through the CW heat exchanger 16 by seawater is performed by the service pump 17 through the TCW heat exchanger 19.

On the other hand, when performing heat removal using a heat removal system other than the normal seawater system during regular inspection due to shortening of regular inspection etc., the switching valve is used.
By opening / closing 46, the cooling water to the reactor and turbine auxiliary cooling water system cooling load 20 and 22 that needs cooling at regular inspection is cooled by the cooling water using the first alternative air-cooled refrigerator 31 Thus, these can be cooled.

According to the present embodiment, the cooling of the reactor auxiliary cooling water system and the turbine auxiliary cooling water system which need to be cooled during the regular inspection using the heat removal system other than the normal seawater system is continued. It is possible to obtain a cooling facility such as a nuclear reactor that can be used.

(Eleventh Embodiment) An eleventh embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
The first alternative air-cooled refrigerator 31 is connected to the cooling water supply and return cooling water pipes 37 from the first alternative air-cooled refrigerator 31 to the emergency core cooling system auxiliary equipment cooling load 24. An alternative pump 39 is installed in a cooling water pipe 37 for supply from the 31 to the emergency core cooling system auxiliary equipment cooling load 24 and a switching valve 46 is connected.

Next, the operation will be described. In the event of a loss of reactor coolant during normal reactor shutdown, at least one emergency core cooling system can supply cooling water. The heat generated from 24 is cooled by seawater supplied from the RHRS pump 7.

However, in the event that a loss of coolant occurs during heat removal using a heat removal system other than the normal seawater system during regular inspection due to shortened regular inspection, etc., the emergency core cooling By supplying cooling water to the system auxiliary equipment cooling load 24 from the first alternative air-cooled refrigerator 31 through the alternative pump 39, coolant can be supplied to the emergency core cooling system auxiliary equipment cooling load 24. Becomes

According to the present embodiment, in the case where cooling is continuously performed during the regular inspection using the alternative cooling water system in addition to the normal cooling water system using seawater, a loss of the coolant in the RPV occurs. Even in this case, it is possible to obtain a cooling facility such as a nuclear reactor capable of supplying coolant to the nuclear reactor.

(Twelfth Embodiment) Referring to FIG. 10, a twelfth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described.
In this embodiment, as shown in FIG. 10, a cooling water supply pipe 37 and a cooling water pipe 37 for return are provided between the emergency power generation equipment cooling load 44 and the first alternative air-cooled refrigerator 31. That is, the alternative pump 39 and the switching valve 46 are connected to the supply cooling water pipe 37 between the first alternative air-cooled refrigerator 31 and the emergency power generation equipment cooling load 44.

Next, the operation will be described. Should an external power supply be lost due to an earthquake or the like when a normal reactor shuts down, the emergency power generation facility cooling load 44 can continue to remove heat by operating at least one system. The heat generated from the emergency power generation facility cooling load 44 is cooled by seawater supplied from the emergency power generation facility cooling seawater pump 40.

Here, due to the shortening of the regular inspection and the like, during the regular heat removal using a heat removal system other than the seawater system during the regular inspection, an external power source was lost due to an earthquake or the like. In this case, the heat removal can be continued by supplying the cooling water from the first alternative air-cooled refrigerator 31 to the emergency power generation facility cooling load 44 through the alternative pump 39.

According to the present embodiment, by using an alternative cooling water system other than the normal cooling water system using seawater,
Even if cooling is continued during regular inspection,
Even if the external power supply is lost due to an earthquake or the like, it is possible to obtain a cooling facility such as a reactor capable of continuing heat removal.

(Thirteenth Embodiment) A thirteenth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIGS. The present embodiment resides in that the alternative cooling water system for the residual heat removal system and the reactor coolant purifying system is a seawater system using a seawater pump exclusively used when the reactor is stopped. Further, in place of the seawater system, an air cooler using the atmosphere as a cooling source or a gas cooling system using a refrigerator is provided.

Here, the first RHR heat exchanger 48 of the residual heat removal system, the second RHR heat exchanger 49, the CUW non-regenerative heat exchanger 11, the RCW cooling load 20 requiring regular inspection cooling, the constant The first alternative air-cooled refrigerator 31 connected to the secondary cooling water pipe for the TCW cooling load 22, the emergency core cooling system auxiliary equipment cooling load 24, and the emergency power generation equipment cooling load 44 that require inspection cooling. Is
In this embodiment, an air cooler using the atmosphere as a cooling source, a refrigerator, or a seawater pump is provided. Here, when installing the seawater pump, water is taken from a standby water intake tank separate from the intake tanks of the RHRS pump 7 and the regular seawater pump 17 of the corresponding plant.

According to the present embodiment, in addition to the normal cooling water system using seawater, a seawater system using a dedicated seawater pump when the reactor is stopped or a gas cooling system using the atmosphere as a cooling source is provided, so that the periodic inspection is performed. Cooling equipment such as a nuclear reactor capable of continuously cooling can be obtained.

(Fourteenth Embodiment) This embodiment relates to a ninth embodiment.
In still another example of the thirteenth to twelfth embodiments, a fourteenth embodiment according to the present invention will be described with reference to FIGS.

This embodiment is different from the ninth to twelfth embodiments in that a plurality of the facilities of the above embodiments are combined, and a replacement pump 39 and a first replacement air-cooled refrigerator are provided.
31 is also used. If necessary, a seawater system using a seawater pump or a gas cooling system using the atmosphere as a cooling source can also be used as in the thirteenth embodiment, instead of the first alternative air-cooled refrigerator 31. I did it.

Next, the operation will be described. Since the operation of this embodiment is a combination of the ninth to twelfth embodiments, the operation is the same as that of the ninth to twelfth embodiments. By providing all the necessary equipment in the equipment, necessary heat removal assumed at the time of regular inspection can be performed. According to the present embodiment, it is possible to obtain a cooling facility such as a nuclear reactor that can continuously perform cooling during regular inspection using a heat removal system other than the normal seawater system.

(Fifteenth Embodiment) A fifteenth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
In the present embodiment, among the facilities in which the facilities in the first to third embodiments are combined, the second substitute pump 52 and the third substitute pump 53 are replaced with a second substitute air-cooled refrigerator. 32 and a third alternative air-cooled refrigerator 38.

That is, in this embodiment, an alternative heat exchanger 25 is installed in which the primary supply side is connected to the FPC pump 12 and the return side is connected to the reactor well 1, and the secondary side of the alternative heat exchanger is installed. Is connected to the secondary cooling water pipe 36 of the second FPC heat exchanger and the cooling water pipe 55 from the third air-cooled refrigerator, and the cooling water pipe 55 is connected to the cooling water pipe 55 through the third replacement pump 53. It is connected to a third alternative air-cooled refrigerator 38. Branching from the cooling water pipe 55, the emergency core cooling system auxiliary equipment cooling load (ECCS load) 24 and the emergency power generation equipment cooling load 44 are connected in parallel.

A cooling water pipe 54 from a second alternative air-cooled refrigerator is connected to the secondary cooling water pipe 41 of the CUW non-regenerative heat exchanger 11, and a second replacement pump is connected to this cooling water pipe 54. A second alternative air-cooled refrigerator 32 is connected via 52.

Here, the first alternative FPC heat exchanger 33,
The second replacement pump 52 cools the CUW non-regenerative heat exchanger 11, the cooling water system cooling load 20 for the reactor auxiliary equipment that requires cooling at regular inspection, and the cooling load 22 for cooling the turbine auxiliary equipment water system that needs cooling at the regular inspection.
And a second alternative air-cooled refrigerator 32 for cooling, a second alternative FPC heat exchanger 34, an alternative heat exchanger 25, an emergency core cooling system auxiliary equipment cooling load 24, and an emergency power generation equipment cooling. Load 44
Is cooled by a third alternative pump 53 and a third alternative air-cooled refrigerator 38.

Next, the operation will be described. This embodiment is the first
Since the same operation as that of the eighth embodiment obtained by combining the sixth embodiment with the sixth embodiment can be obtained, necessary heat removal assumed at the time of regular inspection can be performed. By providing redundancy for alternative cooling and heat removal systems other than
Even if one heat removal system loses its function for some reason, the heat removal can be continued, and the same reliability as the normal heat removal equipment can be maintained.

According to the present embodiment, in addition to the normal cooling water system using seawater, a cooling water system including the second and third air-cooled refrigerators 32 and 38 and the substitute heat exchanger 25 is provided. It is possible to obtain a cooling facility such as a nuclear reactor capable of continuously cooling during regular inspection while maintaining the same reliability as heat removal by the seawater system.

(Sixteenth Embodiment) A sixteenth embodiment of the cooling equipment such as a nuclear reactor according to the present invention will be described with reference to FIG.
In this embodiment, the alternative heat exchanger 25 in the fifteenth embodiment is omitted, and the second alternative pump 52 and the third alternative pump 53 are replaced with the second alternative air-cooled refrigerator 32 and the third alternative pump. In this embodiment, two alternative air-cooled refrigerators 38 are provided, and the same parts as those in FIG. 11 are denoted by the same reference numerals and the description of the same parts will be omitted.

That is, the first RHR heat exchanger 48, CU
The second non-regenerative heat exchanger 11, the RCW cooling load 20 requiring the periodic inspection cooling, and the TCW cooling load 22 requiring the periodic inspection cooling are cooled by the second alternative pump 52 and the second alternative air-cooled refrigeration. The second RHR heat exchanger 49, the emergency core cooling system auxiliary equipment cooling load 24, and the emergency power generation equipment cooling load 44 are cooled by the second RHR heat exchanger 49, the third alternative 9 pump 53 and the third alternative. It is configured to be cooled by an air-cooled refrigerator 38 for use. In addition, in this Embodiment, it can be shared between plants.

Next, the operation will be described. The present embodiment is a fifteenth embodiment.
Since the same operation as that of the embodiment can be obtained, the necessary heat removal assumed at the time of regular inspection can be performed.However, the alternative heat removal system other than the cooling water system using seawater in normal time is provided with redundancy. With this arrangement, even if one of the heat removal systems loses its function for some reason, the heat removal can be continued, and the same reliability as ordinary heat removal equipment can be maintained.

[0119] According to the present embodiment, a regular heat-removal system other than the normal cooling water system using seawater is used to maintain the same reliability as the normal heat removal by the seawater system during regular inspection. It is possible to obtain a cooling facility such as a nuclear reactor that can perform cooling by using the same, and can be shared between plants.

In each of the above embodiments, the alternative cooling system used during regular inspection is used for cooling equipment or cooling for air conditioning even during normal operation, and online maintenance is performed as a spare machine during normal operation. Providing additional functions, such as possible specifications, can provide the same effects as the present invention.

[0121]

According to the present invention, the removal of decay heat generated when the reactor is stopped is switched from the conventional seawater cooling water system to an alternative cooling water system, and the cooling work in the periodic inspection work after the reactor is stopped is interrupted. It can be done continuously without.
In addition, periodic inspections can be shortened by reducing the use and inspection of the seawater cooling water system.

[Brief description of the drawings]

FIG. 1 is a system diagram of equipment and piping for describing a first embodiment of a cooling system for a nuclear reactor or the like according to the present invention.

FIG. 2 is a system diagram of equipment and piping for describing a second embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 3 is a system diagram of equipment and piping for describing a third embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 4 is a system diagram of equipment and piping for describing a fourth embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 5 is a system diagram of equipment and piping for explaining a fifth embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 6 is a system diagram of equipment and piping for describing a sixth embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 7 is a system diagram of equipment and piping for explaining a ninth embodiment of a cooling facility such as a nuclear reactor according to the present invention.

FIG. 8 is a system diagram of equipment and piping for explaining a tenth embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 9 is a system diagram of equipment and piping for explaining an eleventh embodiment of a cooling facility such as a nuclear reactor according to the present invention.

FIG. 10 is a system diagram of equipment and piping for explaining a twelfth embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 11 is a system diagram of equipment and piping for describing a fifteenth embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 12 is a system diagram of equipment and piping for describing a sixteenth embodiment of the cooling equipment such as a nuclear reactor according to the present invention.

FIG. 13 is a system diagram of equipment and piping showing conventional cooling equipment such as a nuclear reactor.

[Explanation of symbols]

1 ... reactor well, 2 ... reactor pressure vessel (RPV), 3
... fuel pool, 4 ... skimmer surge tank, 5 ... RHR pump, 6 ... RHR heat exchanger, 7 ... RHRS pump, 8 ...
CUW pump, 9 ... CUW regenerative heat exchanger, 10 ... CUW-
F / D, 11: CUW non-regenerative heat exchanger, 12: FPC pump, 13: FPC heat exchanger, 14: FPC-F / D, 15: R
CW pump, 16: RCW heat exchanger, 17: regular seawater pump, 18: TCW pump, 19: TCW heat exchanger, 20: RCW cooling load that requires cooling at regular inspection, 21: Cooling is not required at regular inspection RCW cooling load, 23: TCW cooling load that does not require cooling during regular inspection, 24: Emergency core cooling system auxiliary equipment cooling load (ECCS load), 25: Alternative heat exchanger, 26: Alternative FPC pump, 27 ... RCW cooling load, 28 ... TCW cooling load, 29 ... Supply piping from fuel pool to residual heat removal system,
30 ... return pipe from the residual heat removal system to the RPV, 31 ... first alternative air-cooled refrigerator, 32 ... second alternative air-cooled refrigerator,
33: first alternative FPC heat exchanger, 34: second alternative FPC
PC heat exchanger, 35: secondary cooling water pipe of first FPC heat exchanger, 36: secondary cooling water pipe of second FPC heat exchanger, 37: cooling water pipe, 38: third Alternative air-cooled refrigerator,
39: Replacement pump, 40: Emergency power generation equipment cooling seawater pump, 41 ... Secondary cooling water piping of CUW non-regenerative heat exchanger, 42
… Cooling load secondary cooling water pipe of RCW that needs cooling at regular inspection, 43… TCW cooling load secondary cooling water pipe that needs cooling at regular inspection, 44… Cooling load of emergency power generation equipment, 45… F / D bypass pipe, 46 ... switching valve, 47 ... CUW regenerative heat exchanger bypass pipe, 48 ... first RHR heat exchanger, 49 ... second RH
R heat exchanger, 50: secondary cooling water pipe of the first RHR heat exchanger, 51: secondary cooling water pipe of the second RHR heat exchanger,
52 ... second substitute pump, 53 ... third substitute pump, 54
... Cooling water piping from the second alternative air-cooled refrigerator, 55 ... Cooling water piping from the third air-cooled refrigerator, 56 ... Third FPC
Inflow line, 57 ... Reactor well return line.

Claims (22)

[Claims] 1. A cooling system for a reactor for cooling core decay heat generated when a reactor is shut down or heat generated from equipment, a reactor coolant purification system installed in a nuclear power plant, a reactor accessory cooling system, and the like. Alternative cooling water system in addition to the normal cooling water system installed in at least one system selected from the group consisting of a system, a fuel pool cooling purification system, a residual heat removal system, a reactor isolation cooling system, and a turbine auxiliary cooling system. Alternatively, a cooling system for a nuclear reactor or the like characterized by connecting a gas cooling system. 2. A cooling water system for a normal time and an alternative cooling water system are connected to a secondary cooling water pipe of a heat exchanger for a residual heat removal system of the residual heat removal system, and a core decay heat when the reactor is stopped. 2. A cooling system for a nuclear reactor or the like according to claim 1, wherein piping is connected so that any of the cooling water systems can be removed. 3. A normal cooling water system and an alternative cooling water system are connected to a secondary cooling water pipe of a non-regenerative heat exchanger of the reactor coolant purification system of the reactor coolant purification system; The reactor coolant purification system regenerative heat exchanger of the coolant purification system is set to one-sided non-water-flow operation, and the core decay heat at the time of the reactor shutdown together with the residual heat removal system heat exchanger is used for the reactor coolant purification system heat exchanger. 2. A cooling system for a nuclear reactor or the like according to claim 1, wherein the piping is connected so as to be removed by a regenerative heat exchanger. 4. The cooling water system as an alternative to the residual heat removal system and the reactor coolant purifying system is a seawater system using a seawater pump dedicated to when the reactor is stopped.
4. The cooling equipment such as a nuclear reactor according to 3. 5. The cooling water system as an alternative to the residual heat removal system and the reactor coolant purifying system is an air cooler using an atmosphere as a cooling source or a gas cooling system using a refrigerator. 4. Cooling equipment such as a nuclear reactor according to any one of 1 to 3. 6. A pipe connection so as to remove core decay heat generated when the reactor is shut down and to remove heat generated in the spent fuel pool when the reactor is shut down. 5. Cooling equipment such as a nuclear reactor according to 5. 7. A secondary cooling water pipe is connected to a heat exchanger of the system for a cooling load of each of the systems requiring cooling when the reactor is stopped, and the secondary cooling water pipe is connected to the secondary cooling water pipe. A normal cooling water system and an alternative cooling water system are connected, and piping is connected so that a load requiring heat removal when the reactor is stopped is also removed by an alternative cooling water system other than the normal cooling water system. The cooling facility for a nuclear reactor or the like according to claim 1, wherein: 8. The cooling water system for normal use and the alternative cooling water system are connected to the secondary side cooling water pipe for the cooling load of auxiliary equipment of the emergency core cooling system when the reactor is stopped, 2. The cooling equipment for a nuclear reactor or the like according to claim 1, wherein piping is connected so that reactor core flooding can be maintained when the reactor coolant is lost when the reactor is shut down. 9. A cooling water system for normal use and an alternative cooling water system are connected to the secondary-side cooling water pipe for a cooling load of the emergency power generation equipment when the reactor is stopped, and an external power supply is provided when the reactor is stopped. 2. The cooling equipment for a nuclear reactor or the like according to claim 1, wherein piping is connected so that cooling can be continued in the event of loss. 10. A combination of a plurality of at least one cooling facility selected from claims 2 to 5 and at least one cooling facility selected from claims 6 to 9. A cooling system for a nuclear reactor or the like according to claim 2. 11. The fuel pool cooling and purifying system according to claim 1, wherein the normal cooling water system and an alternative cooling water system are connected to a secondary cooling water pipe of a fuel pool cooling and purifying system heat exchanger, and the fuel pool when the reactor is stopped. 2. A cooling system for a nuclear reactor or the like according to claim 1, wherein pipes are connected so as to remove decay heat generated in the cooling water system other than the normal cooling water system. 12. The cooling facility for a nuclear reactor or the like according to claim 11, wherein a pipe bypassing the filtration and desalination apparatus of the fuel pool cooling and purification system is operated. 13. A first heat exchanger and a pump are provided in a fuel pool cooling and purifying system for purifying pool water in a fuel pool,
A second heat exchanger and a pump connected to the fuel pool are provided, and a cooling water system is connected to a secondary-side cooling water pipe of the second heat exchanger, which is generated in the fuel pool when the reactor is stopped. 12. The cooling equipment for a nuclear reactor or the like according to claim 11, wherein piping is connected so that decay heat is removed by the second heat exchanger in addition to the first heat exchanger. 14. The fuel pool cooling / purifying system according to claim 1, wherein a normal cooling water system and an alternative cooling water system are connected, and when the reactor is stopped, the alternative cooling water system is a seawater system using a seawater pump. Cooling equipment such as a nuclear reactor described in 11 or 13. 15. An air cooling system using an air as a cooling source or a gas cooling system using a refrigerator as the cooling water system in the normal state and an alternative cooling water system connected to the fuel pool cooling and purifying system. Item 14. A cooling system for a nuclear reactor or the like according to item 11 or 13. 16. The decay heat removal system of the first heat exchanger or the second heat exchanger is connected to a decay heat removal system so as to remove core decay heat when the reactor is stopped, in addition to heat generated in the fuel pool. 14. The cooling equipment for a nuclear reactor or the like according to claim 11, wherein the cooling equipment is connected. 17. The reactor or the like according to claim 3, wherein pipes are connected so that the core decay heat at the time of reactor shutdown is removed by a non-regenerative heat exchanger of a reactor coolant purification system. Cooling equipment. 18. The cooling equipment for a nuclear reactor or the like according to claim 17, wherein the alternative cooling water system for the reactor coolant purification system comprises the alternative cooling water system according to claim 14 or 15. 19. An alternative cooling water system is connected to a secondary cooling water pipe for a cooling load requiring cooling when the reactor is stopped, and heat generated when the reactor is stopped is transferred to a cooling water system other than the normal cooling water system. 19. The cooling equipment for a nuclear reactor or the like according to claim 11, wherein pipes are connected so as to be removed by an alternative cooling water system. 20. A secondary cooling water pipe having a normal cooling water pipe and an alternative cooling water system connected to the secondary cooling water pipe with respect to the cooling load of the auxiliary equipment of the emergency core cooling system even when the reactor is stopped. 19. The cooling equipment for a nuclear reactor or the like according to claim 11, wherein: 21. A normal cooling water system and an alternative cooling water system are connected to a secondary cooling water pipe with respect to a cooling load of the emergency power generation equipment when the reactor is stopped, and the external power supply is lost when the reactor is stopped. 19.A piping connection so that cooling can be continued by the alternative cooling water system at times.
Reactor cooling equipment as described. 22. A combination of a plurality of at least one cooling facility selected from claims 11 to 15 and at least one cooling facility selected from claims 16 to 21 for the alternative cooling water system. 22. The cooling equipment for a nuclear reactor or the like according to claim 11, wherein piping is connected so as to be shared between the respective systems.