JP2001296387A - Reactor cooling equipment and its operational method - Google Patents

Abstract

PROBLEM TO BE SOLVED: To reduce radiation exposure dose of workers during acces to a reactor pressure vessel in reactor well and remove decay heat without disturbing replacing work of fuel assemblies and control rods. SOLUTION: In a reactor well 4 and a fuel pool 5 constructed in a reactor building, the outlet side of the fuel pool return line 17 of a fuel pool cooling and purifying system line 8 placed downstream the skimer surge line 7 neighboring to the fuel pool 5 is placed in the reactor well 4 and the outlet side of reactor residual heat removal system lines 23 and 24 are placed in the fuel pool 5. By this, radioactive crad contained in reactor water in the reactor pressure vessel 1 is prevented from accumulating on the bottom of the reactor well 4 and so radioactive exposure dose of workers can be reduced.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear power plant, in which, when accessing a reactor pressure vessel, the radiation exposure dose from a reactor well can be reduced and decay heat can be removed without impairing workability. And a method of operating the same.

[0002]

2. Description of the Related Art Referring to FIG. 16, a reactor cooling system of an improved boiling water nuclear power plant will be described. FIG. 16 schematically shows a piping system of a conventional reactor cooling facility.
In FIG. 16, reference numeral 1 denotes a reactor pressure vessel, with a top cover removed.
2 shows a state in which a shroud head, a steam separator, and a steam dryer on the core 2 are removed. Reference numeral 3 schematically indicates an internal pump, a thick line in FIG. 16 indicates a state in which water such as cooling water, reactor water, and pool water is flowing, and a thin line indicates a state in which water is not flowing. I have.

In FIG. 16, the reactor pressure vessel 1 has an outer side surface at an upper end opening below a reactor well 4 built in a reactor building (not shown) via a connecting member (not shown). It is mounted watertight and the lower part of the reactor pressure vessel 1 is supported by a pedestal (not shown). A fuel pool 5 is constructed adjacent to the reactor well 4, and the reactor well 4 and the fuel pool 5 are partitioned by a pool gate 6.

[0004] A plurality of skimmer surge tanks 7 are provided adjacent to the fuel pool 5 and the reactor well 4. The skimmer surge tank 7 is for pouring the supernatant liquid of the water overflowing in the fuel pool 5 and the reactor well 4, and a fuel pool cooling and purifying system (hereinafter, referred to as FPC) line 8 is connected to a lower portion thereof. ing.

[0005] An inlet stop valve 9, an FPC pump 10, an FPC filtration and desalination device 11, an outlet stop valve 12 and an FPC heat exchanger 13 are connected in series to the FPC line 8. A bypass valve on the outlet side of the outlet stop valve 12 on the upstream and downstream sides
An FPC bypass line 15 having 14 is connected.

[0006] FPC pump 10, FPC filtration and desalination unit 11 and FP
Two C heat exchangers 13 are installed in parallel. FP
C Suppression pool purification system (hereafter referred to as SPCU) line that branches from between the filtration and desalination unit 11 and the outlet stop valve 12.
16 are connected. A fuel pool return line 17 is connected to the downstream side of the FPC heat exchanger 13, and the fuel pool return line 17 is connected to an FPC return water injection line 19 via a check valve 18.

An FPC return water injection line 19 is provided in the fuel pool 5, and a return water injection port 20 provided at the lower end thereof is located near the floor of the fuel pool 5. Reactor well 4
Has an SPCU line 16 and is connected to the SPCU line 16 on the outlet side of the FPC filtration and desalination apparatus 11.

An FPC reactor well connection line 22 having a stop valve 21 is provided between the outlet side of the inlet stop valve 9 of the FPC line 8 and the reactor well 4. The inlet side of the inlet stop valve 9 of the FPC line 8 is the RHR of the reactor residual heat removal system (hereinafter referred to as RHR) line connected to the reactor pressure vessel 1.
The (A) system line 23 and the RHR (B or C) system line 24 are connected to an FPC-RHR connection line 28 having stop valves 27a to 27c, respectively.

[0009] The RHR line comprises three systems of first to third systems, and is divided into an RHR (A) system line 23 and an RHR (B or C) system line 24 for the sake of explanation.
An RHR pump 25 and an RHR heat exchanger 26 are sequentially connected in series to the RHR (A) system line 23 and the RHR (B or C) system line 24, respectively.
RHR-FPC Connected via tie line 29. RHR-FPC
RHR return water injection line that branches off from the tie line 29 and reaches the RHR return water inlet 30 near the bottom of the reactor well 4
31 are provided.

In FIG. 16, reference numerals 32, 33, 34a, and 34b denote stop valves, respectively, and reference numeral 35 denotes a reactor water supply system (FDW).
The reactor water supply system 35 has a first water supply sparger line 46 and a second water supply sparger line 47, and these two water supply sparger lines 46 and 47 are provided in the two reactor pressure vessel 1. They are connected to water supply spargers 37, 37, respectively.

The RHR (A) system line 23 is connected to a first water supply sparger line via a branch pipe 38 and a stop valve 39 connected in a branch.
Connected to 46. RHR (B or C) line 24
Is a low pressure water injection system (hereinafter referred to as LPFL) sparger line 45
The LPFL sparger line 45 is connected to a plurality of LPFL spargers 36 provided in the reactor pressure vessel 1.

Here, one system of the RHR line (RHR (A)
The system 23 is connected to a water supply sparger 37 of a reactor water supply system 35, and is returned from the water supply sparger 37 to the reactor pressure vessel 1. The other two systems (RHR (B or C) system) 24 are connected to the LPFL sparger 36. It has been returned to the reactor pressure vessel 1. There are three water supply spargers 37 in one system, six in two systems in total, and one LPFL sparger 36 in one system, two in total.

In FIG. 16, reference numeral 40 is the operation floor level, 41 is the cooling water, 42 is the liquid level of the cooling water 41, 43 is a stop valve, provided on the RHR return water injection line 31, and 44 is also a stop valve. , And an LPFL sparger 36 connected to an LPFL line 45.

[0014]

In a nuclear power plant in which a boiling water reactor is installed, access to the reactor pressure vessel 1 is performed when replacing fuel assemblies and control rods loaded in the reactor core 2 and the like. In this case, since the operation is basically performed from the operation floor level 40, the operation is performed using a long device or the like. Therefore, it is necessary to eliminate the influence of the flow of the cooling water 41 in the reactor well 4 and the fuel pool 5 as much as possible.

In this case, in the current improved boiling water reactor, the decay heat from the fuel in the fuel assembly existing in the reactor pressure vessel 1 or the fuel pool 5 is removed to the reactor pressure vessel 1 while removing the decay heat. It is necessary to eliminate the flow of the cooling water 41 which hinders the workability during the access of the vehicle.

Therefore, the fuel pool water and the cooling water from the reactor well 4 are purified by the FPC filtration and desalination device 11 of the FPC line 8, and the cooling water cooled by the FPC heat exchanger 13 is supplied to the fuel pool 5. It returns from the pool return line 17 through the FPC return water injection line 19. The cooling water cooled by the two-system operation of the RHR (A) system line 23 and the RHR (B or C) system line 24 of the three RHR line facilities is supplied from the RHR return water injection line 31 to the reactor well 4. I'm back.

However, the reactor water flowing out of the reactor pressure vessel 1 contains a radioactive cladding, and the cladding is deposited on the bottom of the reactor well 4 to remove water from the reactor well 4. There is a problem that there is a possibility that the radiation exposure dose to workers during the decontamination work on the bottom of the reactor well 4 may increase.

SUMMARY OF THE INVENTION The present invention has been made to solve the above problems. For example, in a case where a reactor pressure vessel is accessed by remote control, a radiation exposure dose in a reactor well can be reduced without impairing workability. Another object of the present invention is to provide a reactor cooling system capable of efficiently removing decay heat and an operation method thereof.

[0019]

The invention according to claim 1 is
A reactor well and a fuel pool constructed via a pool gate, a fuel pool cooling and purification system line having at least one of the reactor well and the fuel pool as a water source and a filtration and desalination device, and a lower part of the reactor well And a plurality of reactor residual heat removal system lines connected to the reactor pressure vessel and having a heat exchanger, and connected to the downstream side of the fuel pool cooling and purification system line. A return water inlet for the fuel pool return line is provided in the reactor well, and a return water inlet for a downstream return line of the reactor residual heat removal system line is provided in the fuel pool. I do.

According to the present invention, the cooling water purified and cooled by the FPC system is returned to the reactor well, and the cooling water cooled by the RHR system is returned to the fuel pool. This makes it possible to reduce the radiation exposure dose in the reactor well and remove the decay heat without impairing the workability when accessing the inside of the reactor pressure vessel by remote control.

According to a second aspect of the present invention, there is provided a fuel pool cooling system having a reactor well and a fuel pool constructed through a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination apparatus. Purification system line,
A reactor pressure vessel erected below the reactor well,
A plurality of reactor residual heat removal system lines connected to the reactor pressure vessel and having a heat exchanger; and a return water inlet of a fuel pool return line connected downstream of the fuel pool cooling and purification system line. Is provided in the reactor well, a return water inlet of a downstream return line of the reactor residual heat removal system line is provided in the fuel pool, and cooling water of the fuel pool cooling and purification system line is provided in the fuel pool. Alternatively, a switching operation line for returning the cooling water of the reactor residual heat removal system line to the reactor well or the reactor well or the fuel pool is provided.

According to the present invention, the cooling water can be returned to the reactor well or the fuel pool by opening and closing the switching valve of the switching operation line provided in the reactor residual heat removal system line. Further, the cooling water of the fuel pool cooling / purification system line can be returned to the reactor well from another switching operation line.

According to a third aspect of the present invention, at least one of the plurality of reactor residual heat removal system lines is connected to a water supply sparger installed in the reactor pressure vessel and the reactor pressure is reduced. It is characterized by being branched and connected to a low-pressure water injection sparger installed in a container.

According to the present invention, even when the flow rate of the cooling water in the reactor pressure vessel is reduced to return the RHR system cooling water to the reactor pressure vessel, the workability is not affected. It is possible to achieve both removal of decay heat and improvement of workability.

According to a fourth aspect of the present invention, a fuel pool cooling / purifying system return water injection line is connected to the fuel pool return line via a check valve and a stop valve, and provided in the reactor residual heat removal system. An outlet line of the cooling water cooled by the heat exchanger is connected to the fuel pool cooling and purification system return water injection line and the reactor water supply system line.

According to the present invention, the cooling water cooled by the FPC system and the RHR system is returned to the fuel pool, and the cooling water cooled by the RHR system is returned to the water supply sparger. When the reactor pressure vessel is accessed, the radiation exposure dose in the reactor well can be reduced and the decay heat can be removed without impairing the workability.

According to a fifth aspect of the present invention, there is provided a reactor well and a fuel pool constructed via a pool gate, a reactor pressure vessel erected below the reactor well, and connected to the reactor pressure vessel. And a return water inlet for a return line downstream of the reactor residual heat removal system line is provided in the reactor well, and branches off from the reactor residual heat removal system line. A reactor well intake line having an intake port is connected to the upper part of the reactor well.

According to the present invention, the upper water of the reactor well flows into the reactor residual heat removal system line, is cooled by the heat exchanger of this line, and the cooling water is returned to the reactor well. Since the upper water of the reactor well is clean, the radiation exposure dose to the reactor well can be reduced. Also, there is no need to return the cooling water of the reactor residual heat removal system line to the reactor pressure vessel, and workability is not impaired,
Decay heat can be removed.

According to a sixth aspect of the present invention, there is provided a reactor well and a fuel pool constructed through a pool gate, and a first filtration and desalination apparatus using at least one of the reactor well and the fuel pool as a water source. A fuel pool cooling and purifying system line, a reactor pressure vessel erected below the reactor well, and a plurality of reactor residual heat removal system lines connected to the reactor pressure vessel and having a heat exchanger. In addition, a filter or a second filtration and desalination device is provided in the cooling water outlet side piping system of the reactor residual heat removal system line.

According to the present invention, in a nuclear power plant, when remote access to the reactor pressure vessel is performed, the cooling water cooled by the RHR system is purified by a filter or a filter desalination apparatus, and the reactor well is purified. By returning to, the radiation exposure dose in the reactor well can be suppressed low and the decay heat can be removed without impairing the workability.

According to a seventh aspect of the present invention, a reactor well sparger connected to at least one of the return lines is provided in the reactor well, and a cooling water outlet of the reactor well sparger is connected to the reactor pressure vessel. It is characterized by being provided diagonally downward toward the center line and horizontally in the center line.

According to the present invention, by providing the cooling water outlet of the reactor well sparger in an obliquely downward direction toward the center line and in a horizontal direction toward the center line, the radiation exposure dose of the cooling water is suppressed low, and the decay heat is reduced. Can be removed.

The invention according to claim 8 is characterized in that there is provided means for setting the flow direction of water blown out from the low-pressure water injection system sparger installed in the reactor pressure vessel downward.

According to the present invention, by attaching the shielding device for covering the upper and inner sides to the low-pressure water injection sparger,
When the reactor water cooled by the reactor residual heat removal system line is returned to the low-pressure water injection system sparger when accessing the reactor pressure vessel by remote control, the return water must flow directly to the center of the reactor pressure vessel. Therefore, the radiation exposure dose can be reduced and the decay heat can be removed without impairing the workability.

Alternatively, by attaching a plurality of sparger nozzles having a cooling water outlet downward to the lower surface of the low-pressure water injection system sparger, the cooling water is blown out between the reactor pressure vessel and the shroud, and Since the cooling water does not blow out toward the center of the reactor well, it is possible to restrict the cladding from being brought into the reactor well and to reduce the radiation exposure dose in the reactor well. In addition, decay heat can be removed without hindering workability in accessing the reactor pressure vessel by remote control.

The invention according to claim 9 is characterized in that a plurality of diffusers having a large number of cooling water blowing holes are provided in a shelf shape in the fuel pool. According to the present invention, a large amount of cooling water can be returned to the fuel pool without increasing the pipe diameter by providing a plurality of diffusers vertically above and below the fuel pool. Layout can be performed effectively.

According to a tenth aspect of the present invention, a first water supply line and a second water supply line are connected to two systems of water supply spargers installed in the reactor pressure vessel, and these two water supply lines are respectively connected to the first water supply sparger. A reactor coolant purification system line is connected via a check valve and a second check valve, and the reactor coolant purification system line is connected to the first water supply line and the first check valve. And the first check valve is a check valve with a forced open function.

According to the present invention, the coolant can flow in the reverse direction by the check valve having the forced opening function. Therefore, cooling water from the reactor residual heat removal system line is supplied to the first or second water supply sparger line of the reactor water supply system via an electric valve or a water supply system stop valve attached to the reactor coolant purification system line. You can selectively return to the line. The effect on the operation inside the reactor pressure vessel such as refueling can be minimized, and the decay heat can be removed.

The invention according to claim 11 is a fuel pool cooling system having a reactor well and a fuel pool constructed via a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination apparatus. Purification system line,
A reactor pressure vessel erected below the reactor well,
A reactor residual heat removal system line connected to the reactor pressure vessel and having a heat exchanger, the reactor having a regenerative heat exchanger branched from the reactor residual heat removal system line, and a filter desalination device A reactor coolant purification system line is provided, and a reactor coolant purification system return line connected to an outlet side of a filtration and desalination apparatus of the reactor coolant purification system line is connected to the reactor water supply system line. The coolant purification system return line is provided with a reactor coolant purification system bypass line that bypasses the heat exchanger.

According to the present invention, by providing the reactor coolant purification system bypass line and performing the bypass operation of the reactor coolant purification / regeneration heat exchanger, the efficiency of removing decay heat can be improved.

According to a twelfth aspect of the present invention, there is provided a reactor well and a fuel pool constructed via a pool gate, and a filter desalination apparatus and a heat exchanger using at least one of the reactor well and the fuel pool as a water source. A fuel pool cooling and purifying system line, a reactor pressure vessel erected below the reactor well, and a reactor residual heat removal connected to the reactor pressure vessel via a stop valve and sequentially connected to a heat exchanger. The method for operating a reactor cooling system including a system line, wherein a bypass line having a bypass valve is provided in a filtration desalination device of the fuel pool cooling purification system line, and the bypass valve of the bypass line is opened, It is characterized in that the flow rate to the heat exchanger of the fuel pool cooling and purification system line is increased.

According to the present invention, the system flow rate of the fuel pool purification system is increased by opening the bypass valve of the fuel pool purification system filtration and desalination apparatus, and the flow rate of the fuel pool purification system heat exchanger is increased. The heat removal efficiency of the fuel pool purification system can be increased.

According to a thirteenth aspect of the present invention, there is provided a fuel pool cooling system having a reactor well and a fuel pool constructed through a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination apparatus. Purification system line,
A reactor pressure vessel erected below the reactor well,
A plurality of reactor residual heat removal system lines connected to the reactor pressure vessel and having a heat exchanger, and a reactor residual heat removal system connecting the reactor residual heat removal system line and the fuel pool purification system line; In the method for operating a reactor cooling system provided with a tie line for a fuel pool cooling and purification system, the plurality of systems of the residual heat removal system of the reactor include three systems, a first system to a third system, and the first system is a system of the system. The cooling water cooled by the heat exchanger is returned to the reactor water supply system or the fuel pool, the second system returns the cooling water cooled by the heat exchanger of the system to the fuel pool, and the third system is After cooling in the heat exchanger of the system, the fuel pool is returned to the fuel pool, and the fuel pool cooling and purification system line takes in the fuel pool water,
After the purification, it is returned to the reactor well or the equipment temporary storage pool via a suppression pool purification system.

According to the present invention, the cooling operation of the three systems of the residual heat removal system of the reactor is performed and the system flow rate is set to approximately 50% of the rated operation, so that sufficient heat removal capability can be obtained. By returning this to the fuel pool and the water supply sparger, the radiation exposure dose to the reactor well can be reduced.

Further, the fuel pool cooling and purifying system is operated as a purifying operation, and after exiting the filtration / desalination apparatus, it may be returned to the reactor well or the equipment temporary pool adjacent to the reactor well via the suppression pool purifying system. it can.

According to a fourteenth aspect of the present invention, there is provided a fuel pool having a reactor well and a fuel pool constructed through a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination apparatus. A reactor cooling system comprising a cooling purification system line, a reactor pressure vessel erected below the reactor well, and a reactor residual heat removal system line connected to the reactor pressure vessel and having a heat exchanger In the operation method described in (1), the reactor residual heat removal system includes first to third systems, and the heat exchangers provided in each of the first to third systems have at least two heat exchangers.
It is characterized in that it is operated with a base series connection.

According to the present invention, by operating a plurality of reactor residual heat removal system heat exchangers connected in series, the heat removal efficiency of the reactor residual heat removal system line can be increased, and An operation to return from the low pressure water injection system or the water supply sparger to the reactor pressure vessel can be performed.

[0048]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of a reactor cooling system according to the present invention will be described with reference to FIG. FIG.
In FIG. 16, the same parts as those in FIG. 16 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. The present embodiment is different from the conventional example in that a point connecting the downstream side of the fuel pool return line 17 and the downstream side of the RHR-FPC tie line 29 is a junction 48, and FPC return water injection is performed at the junction 48. The line 19 is branched and connected. In addition, a stop valve 49 is provided in the fuel pool return line 17, and further, the fuel pool return line 17 is branched from the outlet side of the check valve 18 and connected to the FPC return water flow line 51 via the stop valve 50, This is because the RHR return water injection line 31 is connected to the FPC return water flow line 51.

That is, in this embodiment, the cooling water washed by the FPC filtration and desalination apparatus 11 and cooled by the FPC heat exchanger 13 is supplied to the fuel pool return line 17, the FPC return water flow line 51 and the RHR return water. It is possible to return the cooling water cooled by the RHR system lines 23 and 24 to the fuel pool 5 from the RHR-FPC tie line 29 to the fuel pool 5 through the FPC return water injection line 19 while returning the cooling water to the reactor well 4 through the injection line 31. Configure the piping system to be able to.

According to the present embodiment, the piping configuration at the junction 48 where the FPC system and the RHR system merge is reviewed, and the cooling water of the FPC system and the RHR system does not merge, and the FPC system is used in the reactor well 4.
The RHR system can perform an operation of returning to the fuel pool 5. As a result, the cooling water returned to reactor well 4 is FP
Since the cleaning is performed by the C filtration and desalination apparatus 11, no cladding is deposited on the reactor well 4, and radiation exposure can be significantly reduced.

On the other hand, from the viewpoint of decay heat removal, by opening the pool gate 6 provided between the reactor well 4 and the fuel pool 5, both the reactor well 4 and the fuel pool 5 are cooled. Thus, total heat removal can be performed. Here, suction of the RHR system is performed from the reactor pressure vessel 1 in both systems in FIG. 1, but one system may be performed from the reactor pressure vessel 1 and the other system may be performed from the fuel pool 5.

In FIG. 1, the intake side of the FPC system is connected to a skimmer surge tank 7 which is connected to the fuel pool 5 and the reactor well 4. The skimmer surge tank 7 has a fuel pool 5 and a reactor well 4.
Since the water overflows and flows in, the water source of the FPC system is the fuel pool 5 and the reactor well 4. However, the configuration of the intake side of the FPC system for realizing the present embodiment is not limited to this, and an intake port of the FPC system is provided above the fuel pool 5 or the reactor well 4 so that the direct fuel pool 5 Alternatively, water may be taken from the reactor well 4. Alternatively, a configuration may be adopted in which an intake port of the FPC system is provided at the bottom of the reactor well 4, and the FPC-reactor well connection line 22 shown by a thin line in FIG. 1 is used for intake of the FPC system. In any case, the FPC system is configured using the fuel pool 5 and / or the reactor well 4 as a water source.

Next, a second embodiment of the reactor cooling system according to the second aspect of the present invention will be described with reference to FIG. In FIG.
The same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. This embodiment is different from the first embodiment in that the first switching line 1 connecting the RHR-FPC tie line 29 and the RHR return injection line 31 and having a first switching valve 103
04. Further, the second switching valve 105 is provided between the junction of the first switching line 104 and the junction 48 on the RHR-FPC tie line 29.

According to the present embodiment, the cooling water in the reactor residual heat removal system lines 23 and 24 is closed by closing the first switching valve 103,
By opening the second switching valve 105, the fuel can be returned from the return water inlet 20 to the fuel pool 5 through the FPC return water injection line 19. Further, the first switching valve 103 is opened, and the second switching valve 103 is opened.
By closing the switching valve 105, the cooling water in the reactor residual heat removal system lines 23 and 24 can be returned to the reactor well 4.

Next, another example of the second embodiment will be described with reference to FIG. 3, the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. In this example, one end of the check valve 18 attached to the fuel pool return line 17 is branched from the inlet side, and the other end is connected to the FPC return water flow line 5.
The second switching line 106 connected to the stop valve 50 attached to 1
Has been established.

According to this example, the cooling water of the fuel pool cooling / purifying system line 8 is passed through the fuel pool return line 17 and
Switching line 106, stop valve 50, FPC return water injection line 51
And can be returned to the reactor well 4 through the RHR return water inlet 30. At this time, the check valve 18 can prevent the cooling water including the clad from the RHR lines 23 and 24 from flowing into the reactor well 4 regardless of the open / close state of the stop valve 49.

Next, a third embodiment of the reactor cooling system according to the third aspect of the present invention will be described with reference to FIG. In FIG.
The same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. The difference between the present embodiment and the first embodiment is that, of the plurality of reactor residual heat removal system lines,
A first or second system connected to a low-pressure water injection system sparger installed in a reactor pressure vessel is connected to a water supply sparger and the low-pressure water injection sparger installed in the reactor pressure vessel. .

That is, a branch pipe 38 branched from the RHR (A) system line 23 and connected to the first water supply sparger line 46 and having a stop valve 39 is provided, and a branch pipe 38 branched from the RHR (B or C) system line 24 is provided. A branch pipe 52 having a stop valve 53 connected to the second water supply sparger line 47 is provided. Thus, RHR
(B or C) It is configured to supply RHR cooling water from the system line 24 to the LPFL sparger line 45 and the second water supply sparger line 47.

Although three RHR systems are provided as described above, conventionally, one RHR system is connected to one system of a water supply system (FDW system), and a single system water supply sparger 37 is connected to the reactor pressure vessel. It has been returned to 1. Water supply sparger 37 is 3 for 1 system
In contrast, six LPFL spargers 36 are installed in one system, whereas a total of six LPFL spargers 36 are installed in one system. Therefore, compared with returning the cooling water from the LPFL sparger 36, the operation in which the cooling water is returned from the water supply sparger 37 has a lower flow velocity in the reactor pressure vessel 1 and the workability is improved.

According to the present embodiment, a system configuration in which one system of the RHR system can be connected to two systems of the water supply system (FPW system) or RH system
By using a system configuration in which the R2 system is connected to the FDW2 system, workability can be maintained even when the flow rate in the reactor pressure vessel 1 is reduced to return the RHR system cooling water to the reactor pressure vessel 1. Elimination of decay heat and improvement of workability can be achieved without adversely affecting the heat resistance.

Next, a fourth embodiment of the reactor cooling system according to the present invention will be described with reference to FIG. In FIG.
The same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. In the present embodiment, for example, in the first embodiment, the RHR filtration desalination is performed on the cooling water outlet side piping system of the RHR heat exchanger 26 of the RHR (A) system line 23 and the RHR (B or C) system line 24. The device 54 is provided via the stop valves 55 and 56. In addition, the RHR filtration desalination unit 54 is bypassed.
An RHR filtration desalination device bypass 57 is provided before and after the stop valves 55 and 56 via a bypass valve 58. When using the RHR filtration and desalination device 54, the bypass valve 58 is closed.

According to the present embodiment, the RHR filtration desalination apparatus
By providing the 54, the radioactive material in the cooling water of the RHR system is removed and the cooling water is purified and returned to the reactor well 4, so that the radiation exposure dose of the reactor well 4 can be reduced. At the same time, the decay heat can be removed. It should be noted that a filter such as a hollow fiber membrane filter can be provided instead of the RHR filtration and desalination device 54. When the radioactivity in the RHR system cooling water is low, the bypass valve 58 is opened and the RH
It can also pass through the R filtration desalination device bypass valve 58.

Next, a fifth embodiment of the reactor cooling system according to the fourth aspect of the present invention will be described with reference to FIG. In FIG.
The same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. This embodiment is different from the first embodiment in that the fuel pool water taken from the fuel pool 5 through the skimmer surge tank 7 is purified by the FPC filtration and desalination device 11 of the FPC system line 8, and the FPC heat exchanger is used. It cools at 13 and returns to the fuel pool 5 through the fuel pool return line 17 and the FPC return water injection line 19.

The reactor water or the fuel pool water in the reactor pressure vessel 1 is also cooled by the RHR system and returned to the fuel pool 5. In this case, one RHR system returns the cooling water cooled by the RHR heat exchanger 26 to the water supply sparger 37. Fuel pool return line
A check valve 18 and a stop valve 49 are connected to 17 in series.

According to the present embodiment, the reactor pressure vessel 1
By reducing the flow rate of return water in the reactor,
The remote exposure workability in the reactor pressure vessel 1 can be improved by reducing the radiation exposure dose and refueling. Further, the flow rate of the return to the water supply sparger 37 is preferably about 50% of the flow rate of the RHR system line in order to limit the flow rate in the reactor pressure vessel 1.

Next, a sixth embodiment of the reactor cooling system according to the fifth aspect of the present invention will be described with reference to FIG. In FIG.
The same parts as those in FIG. 16 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. This embodiment is different from the conventional example in that the RH
A reactor well intake line 59 is connected to the R (A) system line 23 or the RHR (B or C) system line 24, and a reactor well upper intake port 60 is attached to the upper end of the reactor well intake line 59. The FPC connected to the skimmer surge tank 7
One end of a skimmer surge tank intake line 61 is connected to the line 8 from the upstream side of the inlet stop valve 9, and the other end of the skimmer surge tank intake line 61 is connected to the RHR via a stop valve 62.
(A) It is connected to the system line 23 or the RHR (B or C) system line 24.

The fuel pool 5 is provided in the skimmer surge tank 7.
, The clean supernatant water overflows and flows in. The natural convection due to the reactor decay heat raises the temperature of the upper part of the reactor well 4. Therefore, in the present embodiment, the upper water of the reactor well 4 is taken from the upper inlet 60 of the reactor well connected to the RHR system line 23 or 24, or the upper part of the fuel pool 5 is taken from the skimmer surge tank intake line 61. Water is taken and these upper waters are transferred to the RHR system line.
It is cooled by the 23 or 24 RHR heat exchanger 26 and returned to the reactor well 4 again.

According to the present embodiment, since the water quality of the upper part of the reactor well 4 and the upper part of the fuel pool 5 is cleaner than that of the reactor water, the radiation exposure dose of the reactor well 4 can be reduced. Further, there is no need to return the cooling water of the RHR system line to the reactor pressure vessel 1, and the workability of remote operation is not impaired.

Next, a seventh embodiment of the reactor cooling system according to the present invention will be described with reference to FIG. FIG. 8 is a longitudinal sectional view schematically showing the reactor well 4 in FIGS. 1 to 7 by enlarging a portion on the left side from the center line 67. In addition,
Reference numeral 1 partially shows a reactor pressure vessel, and reference numeral 63 schematically shows a reactor well sparger in a longitudinal section. A, B, A, B, and the like are attached from the center point in the reactor well sparger 63 in the arrow direction. C and D indicate the directions of the outlets of the reactor well sparger 63 through which the cooling water blows.

Reference numeral 64 denotes a connecting member for attaching the upper end of the reactor pressure vessel 1 to the lower part of the reactor well 4 and sealing the water with water.
65 is the reactor well corner, and 66 is a jetty. Reactor water is stored in the reactor pressure vessel 1.

In the conventional example, the outlets are provided in the directions of A, B, and C of the reactor well sparger 63, and the cooling water is blown out in this direction. However, there is a problem that the clad accumulates in the reactor well corner portion 65 and causes radiation exposure of workers during the decontamination work after draining the reactor well 4.

Therefore, in the present embodiment, just below the reactor well corner portion 65, that is, the diagonally downward direction toward the center line 67, that is, the diagonally downward direction toward the center line 67, that is, without providing the outlet in the B direction and the diagonal wall direction, that is, the C direction. The outlet is provided in the direction and the horizontal direction toward the center line 67, that is, in the D direction. According to the present embodiment, the cooling water is blown out from the outlets in the direction A and the direction D, so that the clad is less likely to accumulate at the bottom of the reactor well 4, particularly at the corner 65, and the reactor well 4
Radiation of workers at the time of decontamination can be reduced.

Next, an eighth embodiment of the reactor cooling system according to the present invention will be described with reference to FIG. FIG. 9 shows the reactor well 4 and the reactor pressure vessel 1 shown in FIGS.
Are partially enlarged and shown in a schematic longitudinal sectional view. In FIG. 9, reference numeral 68 denotes a shielding device, and 69 denotes a shroud. In this embodiment, the LPFL installed in the reactor pressure vessel 1
The shielding device 68 is attached so as to cover the upper and outer sides of the sparger 36.

In this embodiment, when the cooling water cooled in the RHR (B or C) system line 24 is returned to the reactor pressure vessel 1, LP
It is returned by the FL sparger 36. In this case, the shielding device 68 is attached to the LPFL sparger 36, and the return water from the LPFL sparger 36 falls between the shroud 69 and the reactor pressure vessel 1, and the center of the reactor pressure vessel 1 Blowing in the direction can be prevented. This limits the carry-in of the clad into the reactor well 4, reduces radiation exposure in the reactor well, and removes decay heat without impeding the workability of remotely accessing the reactor pressure vessel. it can.

Next, according to FIGS. 10 (a) and 10 (b), claim 8 will be described.
A ninth embodiment of the reactor cooling equipment according to the present invention will be described. FIG. 10A is a partially schematic sectional view of the reactor well 4 and the reactor pressure vessel 1 as in FIG. 9, and FIG. 10B is a partially enlarged view of the LPFL sparger 36 in FIG. And shown in a perspective view.

In the present embodiment, a plurality of sparger nozzles 70 are attached to the lower surface of the LPFL sparger 36 installed in the reactor pressure vessel 1, and the cooling water outlet 71 of the sparger nozzle 70 is directed downward, that is, directly below. It has been provided.

The sparger nozzle of the conventional LPFL sparger 36 is mounted on the upper surface of the LPFL sparger 36 and is bent from the middle so that the outlet of the cooling water is directed toward the center line of the reactor pressure vessel. On the other hand, in the present embodiment, the LPFL sparger nozzle 70 is attached to the lower surface of the LPFL sparger 36, and the outlet 71 is directed downward, so that the cooling water does not flow toward the center of the reactor pressure vessel 1. .

According to the present embodiment, even if the return of the RHR refueling mode is set to the reactor pressure vessel 1, the problem of fuel sway does not occur. For this reason, it is possible to limit the bringing of the clad into the reactor well and reduce the radiation exposure of the reactor well. Further, since only the sparger nozzle is changed, the amount of remodeling can be reduced.

Next, referring to FIGS. 11 (a) and 11 (b), a ninth aspect will be described.
A tenth embodiment of the reactor cooling equipment according to the present invention will be described. FIG. 11A shows the fuel pool 5 shown in FIGS.
11 (b) is a top view of FIG. 11 (a). In FIGS. 11 (a) and 11 (b), reference numeral 72 denotes a structure in the fuel pool, and a spent fuel storage rack if used, 73 denotes a vertical pipe, 74 denotes a diffuser connected to the vertical pipe 73, and 75 denotes a diffuser provided in the diffuser 74. There are many small holes.

In this embodiment, two vertical pipes 73 are provided in the fuel pool 5 and two diffusers 74 are attached to the upper and lower tiers, and one vertical pipe 73 is provided on each side of the fuel pool internal structure 72. Each book is provided. The diffuser 74 is provided with a large number of small-diameter cooling water outlets 75 for blowing out cooling water. The number of the diffusers 74 is not limited to four and can be adjusted according to the contents and the amount of cooling water. The vertical piping 73 corresponds to the FPC return water injection line 19 in FIG. 1 in the first embodiment, and the diffuser 74 corresponds to the return water injection port 20.

For example, when it is necessary to return a large amount of cooling water to the fuel pool 5 as in the first embodiment, the diameter of the diffuser 74 in the fuel pool 5 increases, and It is disadvantageous in layout. on the other hand,
From the viewpoint of cooling the fuel pool 5, it is desirable to arrange the diffuser 74 at the bottom of the fuel pool 5.

For this reason, as shown in FIGS. 11A and 11B, the diameter of the vertical pipe 73 to the bottom of the fuel pool 5 is increased in order to cope with an increase in the flow rate. On the other hand, the diffuser 74 installed horizontally at the bottom of the fuel pool 5 is provided with two vertical pipes 73, one vertically above and one below, as shown in FIG. 11 (a). As shown, one vertical pipe 73 is provided on each side of the fuel pool internal structure 72.

According to the present embodiment, it is possible to prevent an increase in the pipe diameter, and to make the layout in the fuel pool 5 advantageous.
Therefore, in the nuclear power plant, when the inside of the reactor pressure vessel 1 is accessed by remote control, the radiation exposure dose can be reduced and the decay heat can be removed without impairing the workability.

Although FIG. 11 illustrates the case where the diffusers 74 are provided in two stages, a configuration in which the diffusers 74 are provided in three or more stages in a shelf shape is also possible.

Next, an eleventh embodiment of the reactor cooling equipment according to the tenth aspect of the present invention will be described with reference to FIG. In this embodiment, as shown in FIG. 12, both the A and B systems of the water supply sparger 37 in the reactor pressure vessel 1 are provided with a reactor coolant purifying system (hereinafter referred to as CUW) 76 and stop valves 77 and CUW. It is connected via the system line 78, the stop valve 79, the check valves 80, 81, 82 and the water supply stop valve 83. In particular, in the water supply system (A system), a check valve with a forced operation function is used instead of the check valve 80. The stop valve 84 is provided.

The check valve 84 with a forced operation function refers to a check valve with a handle capable of forcibly opening the flow of purified water not only in one direction but also in the reverse direction if necessary. I have. In FIG. 12, reference numeral 85 denotes a reactor containment vessel, which is partially shown. The reactor water supply system (A system) is RHR
(A) It is branched and connected to the system line 23.

In the conventional example, the RHR (A) system line 23 is a water supply system.
Although it is configured to return only to the first water supply sparger 46 of the first embodiment, in the present embodiment, the check valve 84 with a forced operation function is provided.
Is provided, and the check valve 84 is forcibly opened, so that RH
R (A) Return of cooling water from system line 23 to reactor water supply system 35
The first water supply sparger line (A system) 46 and the second water supply sparger line (B system) 47 can be returned.

According to the present embodiment, the cooling water from the RHR system is supplied to the first water supply sparger (A system) 46 or the second water supply by the stop valve 79 or the water supply stop valve 83 attached to the CUW system line 78. The decay heat can be selectively returned to the sparger (B system) 47, and the decay heat can be removed while minimizing the influence of the work inside the reactor pressure vessel 1 such as fuel exchange. Note that the stop valve 79 or the water supply stop valve 83 may be a manual valve or an electric valve. In the latter case, the operability can be improved by using a motorized valve.

Next, a twelfth embodiment of the reactor cooling system according to the present invention will be described with reference to FIG. In FIG.
The same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. The difference between this embodiment and the first embodiment is that the CUW regenerative heat exchangers 86 and CUW are branched from the suction port of the RHR pump 25 of the RHR (B or C) system line 24 to the upstream side.
Non-regenerative heat exchanger 87, CUW pump 88 and CUW filtration and desalination equipment
89 is that the CUW system line 78 connected in series is connected, and the CUW return line 93 is connected to the reactor water supply system 35.

The CUW regenerative heat exchanger 86 is connected to the CUW return line 93 via a stop valve 90, and is branched from the outlet side of the CUW filtration and desalination unit 89 to the CUW return line 93. Connect line 91 and CUW bypass line
That is, a bypass valve 92 is provided at 91.

According to the present embodiment, the CUW regenerative heat exchanger
By operating by bypassing the 86, when accessing the reactor pressure vessel 1 by remote control at a nuclear power plant, the radiation exposure dose can be reduced without impairing the workability, and the decay heat removal efficiency can be increased. be able to.

Next, a first embodiment of the operation method of the reactor cooling equipment according to the twelfth aspect of the present invention will be described with reference to FIG. In the first embodiment of the reactor cooling equipment according to the first aspect of the present invention, the bypass valve 14 of the FPC filtration and desalination apparatus 11 is shown in a closed state as shown in FIG. The embodiment is characterized in that the operation is performed with the bypass valve 14 opened as shown in FIG. Bypass valve 14
, The flow of the fuel pool water discharged from the FPC pump 10 to the FPC filtration and desalination device 11 and the flow to the FPC bypass line 15 are added, and the flow flowing into the FPC heat exchanger 13 increases. .

Accordingly, the cooling water cooled by the FPC heat exchanger 13 flows from the fuel pool return line 17 through the RHR return water injection line 31 into the reactor well 4 and into the reactor pressure vessel 1. Flow in.

According to the present embodiment, the FPC filtration desalination apparatus
By operating the bypass valve 11 in the open state, the FPC
By increasing the system flow rate of the system and increasing the flow rate of the FPC heat exchanger 13, the heat removal efficiency of the FPC system line can be increased. Therefore, when accessing the reactor pressure vessel by remote control in a nuclear power plant, radiation exposure dose can be reduced and decay heat can be removed without impairing workability.

Next, a second embodiment of the method for operating the reactor cooling equipment according to the invention will be described with reference to FIG. 14, the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. In FIG. 14, RHR (A)
The system line 23 is called a first system, the system B of the RHR (B or C) system line 24 is called a second system, and the system C is also called a third system.

In this embodiment, the cooling water cooled in the first system is returned to the reactor water supply system 35, and the cooling water cooled in the second system is supplied from the RHR-FPC tie line 29 to the FPC return water injection line 19
Then, the fuel pool 5 is returned to the fuel pool 5, the fuel pool water is taken in the third system, cooled by the RHR heat exchanger 26, and then returned to the fuel pool 5. The FPC line 8 takes fuel pool water, purifies it with the FPC filtration and desalination unit 11, and then
An operation of returning from the line 16 to the reactor well 4 or an equipment temporary storage pool (not shown) provided adjacent to the reactor well 4 is performed.

According to this embodiment, the decay heat is removed by RH
The operation is performed in the R heat exchanger 26, and the FPC system is an operation method having only a purification function. Therefore, it is necessary to use the three RHR systems for cooling operation and to operate the system at a flow rate of about 50% of the rated value so that the system has sufficient heat removal capability and returns this to the fuel pool 5 and the reactor water supply system 35. Thus, radiation exposure of the reactor well 4 can be reduced.

Further, the FPC system is operated as a purification operation, and when the FPC system flows out of the FPC filtration and desalination apparatus 11, it can be returned to the reactor well 4 or the equipment temporary storage pool via the SPCU system line 16. Thereby, when accessing the reactor pressure vessel 1 by remote control in a nuclear power plant, radiation exposure dose can be reduced and decay heat can be removed without impairing workability.

Next, a third embodiment of the method for operating a reactor cooling system according to the invention will be described with reference to FIG. 15, the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. In FIG. 15, RHR (A)
A connection line 94 connecting the RHR heat exchangers 26 of the system line 23 and the RHR (B or C) system line 24 in series between the outlet side and the inlet side is connected via a stop valve 95. RHR pump 25
An RHR check valve 96 is connected to the discharge side, and a heat exchanger outlet side stop valve 97 is connected to the outlet side RHR system line of the RHR heat exchanger 26.

The RHR heat exchanger bypass line 98 is connected by branching from the outlet side of the RHR check valve 96 and the outlet side of the heat exchanger outlet side stop valve 97, and a bypass valve 99 is connected to the bypass line 98. Attach. RHR Stop valve on heat exchanger connection line 94
Radioactive waste treatment system tie line 10
0, and the radioactive waste treatment system tie line 100 is connected to a radioactive waste treatment facility 102 via a stop valve 101.

According to this embodiment, the RHR heat exchanger 26 of the RHR (A) system line 23 and the RHR (B or C) system line 24, the radioactive waste treatment system tie line 100, and the RHR heat exchanger bypass line By connecting the RHR heat exchangers 26 in series, the efficiency of removing decay heat can be increased by operating the plurality of RHR heat exchangers 26 in series, without impairing workability.
Radiation exposure dose can be reduced.

Although FIG. 13 shows an example in which the return of the RHR system cooling water is made to be the fuel pool 5, an operation of returning from the LPFL sparger 36 or the feed water sparger 37 to the reactor pressure vessel 1 can also be performed.

[0103]

According to the present invention, when accessing the reactor pressure vessel in a nuclear power plant, the radiation exposure dose in the reactor well is reduced and the decay heat is removed without impairing the workability. It can be performed.

[Brief description of the drawings]

FIG. 1 is a system diagram showing a first embodiment of a reactor cooling facility according to the present invention.

FIG. 2 is a system diagram showing a second embodiment of the reactor cooling equipment according to the present invention.

FIG. 3 is a system diagram showing another example of the second embodiment.

FIG. 4 is a system diagram showing a third embodiment of the reactor cooling equipment according to the present invention.

FIG. 5 is a system diagram showing a fourth embodiment of the reactor cooling equipment according to the present invention.

FIG. 6 is a partial sectional view showing a fifth embodiment of the reactor cooling equipment according to the present invention.

FIG. 7 is a schematic sectional view showing a sixth embodiment of the reactor cooling system according to the present invention.

FIG. 8 is a partial sectional view showing a seventh embodiment of the reactor cooling equipment according to the present invention.

FIG. 9 is a schematic sectional view showing an eighth embodiment of a reactor cooling system according to the present invention.

FIG. 10 (a) is a ninth reactor cooling facility according to the present invention.
FIG. 2B is a schematic cross-sectional view showing the embodiment, and FIG. 2B is an enlarged perspective view showing the LPFL sparger in FIG.

FIG. 11 (a) is a tenth embodiment of the reactor cooling system according to the present invention.
FIG. 4B is a longitudinal sectional view showing a part of the embodiment, and FIG. 6B is a top view of FIG.

FIG. 12 is a system diagram showing an eleventh embodiment of a reactor cooling system according to the present invention.

FIG. 13 is a system diagram for explaining a twelfth embodiment of a reactor cooling facility according to the present invention and a first embodiment of a method of operating the reactor cooling facility.

FIG. 14 is a system diagram for explaining a second embodiment of the operation method of the reactor cooling equipment according to the present invention.

FIG. 15 is a system diagram for explaining a third embodiment of the operation method of the reactor cooling equipment according to the present invention.

FIG. 16 is a system diagram showing a conventional reactor cooling facility.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 ... Reactor pressure vessel, 2 ... Reactor core, 3 ... Internal pump, 4 ... Reactor well, 5 ... Fuel pool, 6 ... Pool gate, 7 ... Skimmer surge tank, 8 ... Fuel pool cooling and purification system (FPC) line , 9 ... inlet stop valve, 10 ... FPC pump, 11 ... FPC filtration and desalination device, 12 ... outlet stop valve, 13 ... FPC
Heat exchanger, 14 ... bypass valve, 15 ... FPC bypass line,
16… suppression pool purification system (SPCU) line, 17…
Fuel pool return line, 18 ... check valve, 19 ... FPC return water injection line, 20 ... return water inlet, 21 ... stop valve, 22 ... FPC −
Reactor well connection line, 23… RHR (A) system line, 24
… RHR (B or C) system line, 25… RHR pump, 26… RH
R heat exchanger, 27 (27a-27c) ... stop valve, 28 ... FPC-RHR
Connection line, 29… RHR-FPC tie line, 30… RHR Return water inlet, 31… RHR Return water injection line, 32, 33, 34, 34
a, 34b: Stop valve, 35: Reactor water supply system (FDW), 36: Low pressure injection system (LPFL) sparger, 37: Water supply sparger, 38
... Branch pipe, 39 ... Stop valve, 40 ... Operation floor level, 41 ... Cooling water, 42 ... Liquid level, 43,44 ... Stop valve, 45 ... LPFL
Sparger line, 46 ... first water sparger line,
47 ... second water supply sparger line, 48 ... confluence, 49, 50
… Stop valve, 51… FPC return water flow line, 52… Branch pipe, 53
… Stop valve, 54… RHR filtration desalination equipment, 55, 56… Stop valve, 57
… RHR filtration desalination equipment bypass, 58… Bypass valve, 59… Reactor well intake line, 60… Reactor well upper intake
61 ... Skimmer surge tank intake line, 62 ... Stop valve, 63 ...
Reactor well sparger, 64 ... connecting member, 65 ... reactor well corner, 66 ... jetty, 67 ... center line, 68 ... shielding device,
69 ... shroud, 70 ... sparger nozzle, 71 ... outlet, 72 ... fuel pool internal structure, 73 ... vertical piping, 74 ... diffuser, 75 ... cooling water outlet, 76 ... CUW system, 77 ... stop valve, 78 ... CUW system line, 79 ... stop valve, 80, 81, 82 ... check valve, 83 ... water supply system stop valve, 84 ... check valve with forced operation function,
85… Reactor containment vessel, 86… CUW Regenerative heat exchanger, 87… CUW
Non-regenerative heat exchanger, 88… CUW pump, 89… CUW filtration desalination device, 90… Stop valve, 91… CUW bypass line, 92… CUW bypass valve, 93… CUW return line, 94… RHR heat exchanger connection line , 95 ... stop valve, 96 ... RHR check valve, 97 ... heat exchanger outlet stop valve, 98 ... RHR heat exchanger bypass line, 99 ... bypass valve, 100 ... radioactive waste treatment system tie line, 101
... stop valve, 102 ... radioactive waste treatment equipment, 103 ... first switching valve, 104 ... first switching line, 105 ... second switching valve,
106 second switching line.

Continued on the front page (51) Int.Cl. ⁷ Identification symbol FI Theme coat II (Reference) G21D 1/00 G21D 1/00 Y (72) Inventor Richi Kuroda 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Toshiba Corporation Inside Yokohama Office (72) Inventor Takuji Takayama 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Inside Toshiba Yokohama Office (72) Inventor Minoru Kobayashi 8 Shin-Sugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture Toshiba Yokohama Business Co., Ltd. In-house (72) Inventor Yuji Yamamoto 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Inside Toshiba Yokohama Office

Claims (14)

[Claims] 1. A reactor pool and a fuel pool constructed via a pool gate, a fuel pool cooling and purification system line having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination device, The fuel pool cooling and purifying system line, comprising: a reactor pressure vessel erected below a reactor well; and a plurality of reactor residual heat removal system lines connected to the reactor pressure vessel and having a heat exchanger. A return water inlet of a fuel pool return line connected to a downstream side of the reactor pool is provided in the reactor well, and a return water inlet of a downstream return line of the reactor residual heat removal system line is provided in the fuel pool. A reactor cooling facility, characterized in that: 2. A reactor pool and a fuel pool constructed via a pool gate, a fuel pool cooling and purification system line having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination device, The fuel pool cooling and purifying system line, comprising: a reactor pressure vessel erected below a reactor well; and a plurality of reactor residual heat removal system lines connected to the reactor pressure vessel and having a heat exchanger. A return water inlet of a fuel pool return line connected to a downstream side of the reactor is provided in the reactor well, and a return water inlet of a downstream return line of the reactor residual heat removal system line is provided in the fuel pool. Returning the cooling water of the fuel pool cooling and purification system line to the fuel pool or the reactor well, or transferring the cooling water of the reactor residual heat removal system line to the reactor well or the reactor well. A cooling operation line for returning the fuel to the fuel pool. 3. At least one of the plurality of reactor residual heat removal system lines is connected to a feed water sparger installed in the reactor pressure vessel and installed in the reactor pressure vessel. 3. The reactor cooling equipment according to claim 1, wherein the reactor cooling equipment is branched and connected to a low-pressure water injection sparger. 4. A fuel pool cooling / purifying system return water injection line is connected to the fuel pool return line via a check valve and a stop valve, and the fuel pool is cooled by a heat exchanger provided in the reactor residual heat removal system. 2. The reactor cooling system according to claim 1, wherein a cooling water outlet line is connected to the fuel pool cooling purification system return water injection line and the reactor water supply system line. 5. A reactor well and a fuel pool constructed through a pool gate, a reactor pressure vessel erected below the reactor well, and a reactor residual heat removal connected to the reactor pressure vessel. And a return water inlet of a return line downstream of the reactor residual heat removal system line is provided in the reactor well, and the reactor well is branched from the reactor residual heat removal system line. A reactor well intake line having an intake port at the top of the reactor. 6. A reactor pool cooling and purifying system line having a reactor well and a fuel pool constructed via a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a first filtration and desalination apparatus. A reactor pressure vessel erected below the reactor well, and a plurality of reactor residual heat removal system lines connected to the reactor pressure vessel and having a heat exchanger. A reactor cooling facility comprising a filter or a second filtration and desalination device provided in a cooling water outlet piping system of a heat removal system line. 7. A reactor well sparger connected to at least one of the return lines is provided in the reactor well, and a cooling water outlet of the reactor well sparger is obliquely downwardly directed toward a center line of the reactor pressure vessel. The reactor cooling equipment according to claim 1, wherein the reactor cooling equipment is provided in each of a direction and a horizontal direction toward the center line. 8. The reactor cooling system according to claim 1, further comprising means for setting a flow direction of water blown out from a low-pressure water injection sparger installed in the reactor pressure vessel downward. Facility. 9. The reactor cooling equipment according to claim 1, wherein a plurality of diffusers having a plurality of cooling water blowing holes are provided in the fuel pool in a shelf shape. 10. A first water supply line and a second water supply line are connected to two water supply spargers installed in the reactor pressure vessel, and these water supply lines are respectively connected to a first check valve and a second check valve. Connected to a reactor coolant purification system line via a check valve, and connected to the reactor coolant purification system line between the first water supply line and the first check valve. 7. The reactor cooling equipment according to claim 1, wherein the first check valve is connected to a heat removal system line, and the first check valve is a check valve with a forced opening function. 11. A reactor pool cooling and purifying system line having a reactor well and a fuel pool constructed through a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination device, A reactor pressure vessel erected below the reactor well, and a reactor residual heat removal system line connected to the reactor pressure vessel and having a heat exchanger, branching off from the reactor residual heat removal system line A reactor coolant purification system line having a regenerative heat exchanger and a filter desalination unit connected to the reactor coolant purification system line connected to the outlet side of the filter desalination unit of the reactor coolant purification system line is provided. A reactor line connected to the reactor water supply system line, and a reactor coolant purification system bypass line for bypassing the heat exchanger in the reactor coolant purification system return line. Furnace cooling equipment. 12. A fuel pool cooling and purifying system having a reactor well and a fuel pool constructed via a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a filter desalination device and a heat exchanger. A line, a reactor pressure vessel erected below the reactor well, and a reactor residual heat removal system line connected to the reactor pressure vessel via a stop valve and sequentially connected with a heat exchanger. In the method for operating a reactor cooling facility, a bypass line having a bypass valve is provided in a filtration and desalination apparatus of the fuel pool cooling / purifying system line, and the bypass valve of the bypass line is opened to thereby form the fuel pool cooling / purifying system line. A method for operating a reactor cooling facility, characterized by increasing the flow rate to a heat exchanger. 13. A reactor pool cooling and purifying system line having a reactor well and a fuel pool constructed through a pool gate, and having at least one of the reactor well and the fuel pool as a water source and having a filtration and desalination apparatus. A reactor pressure vessel erected below the reactor well, a plurality of reactor residual heat removal system lines having a heat exchanger connected to the reactor pressure vessel, the reactor residual heat removal system line, In a method for operating a reactor cooling facility having a tie line for a reactor residual heat removal system and a fuel pool cooling and purification system that communicates with a fuel pool purification system line, the plurality of reactor residual heat removal systems are first to third. The first system returns the cooling water cooled by the heat exchanger of the system to the reactor water supply system or the fuel pool, and the second system cools the cooling water by the heat exchanger of the system. Returned cooling water to the fuel pool,
The third system is cooled by the heat exchanger of the system and then returned to the fuel pool. The fuel pool cooling / purifying system line takes in and purifies the fuel pool water, and then passes through the suppression pool purifying system. A method for operating a reactor cooling facility, comprising returning the reactor to the reactor well or the equipment temporary storage pool. 14. A reactor pool and a fuel pool constructed through a pool gate, a fuel pool cooling and purification system line having at least one of the reactor well and the fuel pool as a water source and having a filter and desalination device, A method for operating a reactor cooling facility comprising a reactor pressure vessel erected at a lower portion of the reactor well and a reactor residual heat removal system line having a heat exchanger connected to the reactor pressure vessel, The reactor residual heat removal system is composed of three systems, a first system to a third system, and is operated by connecting at least two heat exchangers provided in each of the first system to the third system in series. A method for operating a reactor cooling facility, characterized by: