JP7293166B2 - nuclear power plant - Google Patents

Description

The present invention relates to nuclear power plants.

BACKGROUND ART There is known a nuclear power plant provided with a blowout panel for the purpose of releasing steam outside the building when a high-energy pipe such as a main steam pipe breaks (see Patent Document 1). In Patent Document 1, a nuclear power plant in which a blowout panel 4 is provided in each of the reactor building and the turbine building, and a plurality of blowout panels 7 are provided in the main steam pipe tunnel room connecting the reactor building and the turbine building. A power plant is disclosed.

In the nuclear power plant described in Patent Literature 1, when the main steam pipe of the main steam pipe tunnel room is broken, steam is discharged outside the building through two blowout flow paths. When the blowout panel 7 of the main steam pipe tunnel room is opened, the first blowout flow path is a flow path through which steam flows from the main steam pipe tunnel room into the turbine building and the blowout panel 4 of the turbine building. is opened to form a flow path through which the steam that has flowed into the turbine building is discharged outside the turbine building. By opening the blowout panel 7 of the main steam pipe tunnel room, the second blowout channel is a channel through which steam flows from the main steam pipe tunnel room into the reactor building and a blowout of the reactor building. When the panel 4 is opened, the steam flowed into the reactor building is discharged outside the reactor building.

JP-A-63-223592

In the nuclear power plant described in Patent Document 1, when the main steam pipe is broken and the blowout panel of the main steam pipe tunnel room is opened, the reactor building and the turbine building are communicated, and the reactor building is connected to the turbine building. steam flows into the When the reactor building and turbine building are in communication, an event such as a fire that occurs in the reactor building may propagate to the turbine building, causing damage to the machinery in the turbine building, i.e., another system different from the system of the broken piping. machine may be adversely affected. For this reason, when forming a flow path (blow-out flow path) for discharging steam to the outside when the piping that contains the steam generated in the reactor pressure vessel or the reactor water breaks, other There is a desire to limit the adverse effects on system machinery.

SUMMARY OF THE INVENTION An object of the present invention is to provide a nuclear power plant that can release steam to the outside of the building when a pipe is broken while suppressing adverse effects on machines of other systems.

A nuclear power plant according to one aspect of the present invention is a nuclear power plant comprising a reactor building that houses a reactor containment vessel, wherein the reactor building is a reactor pressure vessel provided inside the reactor containment vessel. a main steam pipe that guides the steam generated in the reactor pressure vessel to the turbine building; a main steam pipe room that is provided on the side of the reactor containment vessel and in which the main steam pipe is disposed; a pool provided above the main steam pipe room, the main steam tunnel forming a main steam tunnel room in which the main steam pipe extending from the main steam pipe room toward the turbine building is disposed. A formation portion is provided, and the main steam tunnel formation portion includes a pipe housing portion communicating with the main steam pipe chamber and forming a pipe housing chamber through which the main steam pipe passes, and a pipe housing portion extending upward or laterally from the pipe housing chamber. a first flow path forming portion that forms a flow path that connects to the main steam tunnel chamber; a first blowout panel that closes a first steam outlet provided in the first flow path forming portion; and a partition wall that airtightly partitions the main steam pipe, and the main steam pipe is arranged so as to be led into the turbine building through the partition wall, and the nuclear power plant has a main steam pipe room When the main steam pipe of is broken, the steam released from the broken portion of the main steam pipe is guided from the main steam pipe chamber to the main steam tunnel chamber, and the internal pressure of the main steam tunnel chamber rises. By opening the first blowout panel, a first blowout passage is formed through which the steam in the main steam tunnel chamber is discharged to the outside through the first steam outlet , and the reactor building is connected to the machinery and the nuclear reactor. A guide pipe is arranged to guide steam or reactor water generated in the reactor pressure vessel to the machine, forming a machine room provided on the side of the reactor containment vessel and a flow path communicating with the machine room. and a second blowout panel that closes the second steam outlet provided in the second flow path forming part, and the nuclear power plant includes the guide in the machine room When the pipe is broken, the steam released from the broken part of the guide pipe is guided from the machine chamber to the flow channel of the second flow channel forming part, and the internal pressure of the second flow channel forming part increases. By opening the second blowout panel, a second blowout flow path is formed for discharging the steam in the second flow path forming portion to the outside through the second steam outlet portion, and the second blowout flow path is , an independent channel that does not communicate with the first blowout channel.

Advantageous Effects of Invention According to the present invention, it is possible to provide a nuclear power plant capable of releasing steam to the outside of the building when a pipe breaks while suppressing adverse effects on machines of other systems.

Schematic side cross-sectional view showing the configuration of a nuclear power plant. FIG. 2 is a schematic cross-sectional view taken along the line II-II of FIG. 1 and shows the main steam pipe floor. FIG. 1 is a schematic cross-sectional view taken along line III-III in FIG. 1 and shows an operating floor. It is a figure which shows the modification of a 1st flow-path formation part, and shows a main steam piping chamber floor. It is a figure which shows another modification of a 1st flow-path formation part, and shows a main steam piping chamber floor. It is a figure which shows another modification of a 1st flow-path formation part, and shows an operating floor. FIG. 10 is a schematic side cross-sectional view showing the configuration of a nuclear power plant according to Modification 2; FIG. 11 is a schematic cross-sectional plan view of the nuclear power plant according to modification 3-1, showing an operating floor.

A nuclear power plant 100 according to an embodiment of the present invention will be described with reference to the drawings. FIG. 1 is a schematic side cross-sectional view showing the configuration of a nuclear power generation facility 100. As shown in FIG. 2 is a schematic cross-sectional view taken along the line II-II of FIG. 1 and shows the main steam piping room floor, and FIG. 3 is a schematic cross-sectional view taken along the line III-III of FIG. 1 and shows the operating floor.

As shown in FIGS. 1 to 3, a nuclear power generation facility 100 includes a reactor building 1 that houses a reactor containment vessel 2, a turbine building 6 that houses a turbine (not shown), and a reactor building 1 and a turbine building. and a main steam tunnel building 7 provided between 6. As shown in FIG. 1, the reactor building 1 is built on the reactor building foundation 1a, the turbine building 6 is built on the turbine building foundation 6a, and the main steam tunnel building 7 is built on the main steam tunnel building foundation 7a. built on top.

A reactor building 1 is constructed of reinforced concrete, and a reactor containment vessel 2 is formed inside an outer shell. The reactor containment vessel 2 is a cylindrical structure with a diameter of about 30 m and has a cylindrical side wall 2a. The reactor containment vessel 2 is formed integrally with the outer shell of the reactor building 1 . A reactor pressure vessel 31 that houses the reactor core is installed inside the reactor containment vessel 2 .

The reactor containment vessel 2 has a thick reinforced concrete structure so that it can withstand high pressures and vibrations. A space inside the containment vessel 2 is divided into an upper drywell 19 , a lower drywell 20 and a pressure suppression chamber 21 by a diaphragm floor 18 and the like. The pressure suppression chamber 21 has a pressure suppression pool filled with cooling water and a wet well that is a space above the pool.

The reactor building 1 has an operating floor 22a provided above the reactor containment vessel 2, an operating floor wall 22b rising from the operating floor 22a, and a ceiling 22c provided above the operating floor 22a. An operating floor area 22 is defined by 22a, an operating floor wall 22b and a ceiling 22c. The structures (operating floor 22a, operating floor wall 22b, and ceiling 22c) forming the operating floor area 22 are supported by frame walls 48, 49 and the like rising from the reactor building foundation 1a.

A spent fuel storage pool 23 and a device temporary storage pool 24 are provided on the operating floor 22a. The spent fuel storage pools 23 and equipment temporary storage pools 24 are arranged one by one on both sides (left and right sides in the figure) of the reactor well 25 above the reactor containment vessel 2 . The equipment temporary storage pool 24 is filled with water for radiation shielding, and has a space for temporarily storing equipment (steam separator, steam dryer, etc.) taken out of the reactor pressure vessel 31 during periodic inspections. have

The spent fuel storage pool 23 is filled with cooling water that also serves as radiation shielding, and the spent fuel assemblies taken out from the reactor pressure vessel 31 are placed in the spent fuel storage racks. be done. The spent fuel storage pool 23 also has a space for temporarily storing control rods taken out of the reactor pressure vessel 31 during fuel replacement.

A concrete shielding plug 26 is installed at the top of the reactor well 25 to act as a radiation shield to the operating floor area 22, and the reactor well 25 is filled with water. A portion of the spent fuel storage pool 23 and a portion of the equipment temporary storage pool 24 are positioned above (directly above) the reactor containment vessel 2 . The spent fuel storage pool 23 and reactor well 25 are separated by a spent fuel storage pool gate 27 . The equipment temporary storage pool 24 and the reactor well 25 are partitioned by the equipment temporary storage pool gate 28 .

On the outer periphery (lateral side) of the reactor containment vessel 2 in the reactor building 1, there are a main steam pipe room 40 whose bottom is set at substantially the same level as the ground level (ground surface) GL, and a main steam pipe room 40 which is lower than the ground level GL. Machine rooms 41, 42 are provided with bottoms provided at positions.

A machine room 41 provided on the basement floor is a room located between the reactor containment vessel 2 and the main steam tunnel building 7 . Machines such as an RCIC (Reactor Core Isolation Cooling system) pump 63 and RCIC steam pipes 61 connected to the RCIC pump 63 are arranged in the machine room 41 . A machine room 42 provided on the basement floor is a room located on the opposite side of the machine room 41 so that the reactor containment vessel 2 is sandwiched between the machine room 41 and the machine room 42 . Machines such as a CUW pump 64 and CUW pipes 62 are arranged in the machine room 42 . The machine room 41 and the machine room 42 communicate with each other through a communication path (not shown) formed along the outer circumference of the containment vessel 2 . The main steam pipe room 40 is a room located above (directly above) the machine room 41 , and is located below (directly below) part of the equipment temporary placement pool 24 . In other words, the equipment temporary placement pool 24 is provided above (directly above) the main steam pipe chamber 40 .

The reactor pressure vessel 31 includes a main steam pipe 50 that guides the steam generated in the reactor pressure vessel 31 to the turbine building 6 , and a condenser (not shown) of the turbine building 6 . A water supply pipe (not shown) for guiding water is connected. A plurality of pipes including an RCIC steam pipe 61 and a CUW pipe 62 are connected to the reactor pressure vessel 31 .

The reactor water supplied to the core by a recirculation pump (not shown) is heated by the heat generated by the nuclear fission of the nuclear fuel material in the fuel assemblies loaded in the core, and part of it becomes steam. This steam is led from the reactor pressure vessel 31 through the main steam pipe 50 to a turbine (not shown) arranged in the turbine building 6 to rotate the turbine. Steam discharged from the turbine is condensed into water in a condenser (not shown). This water is supplied to the reactor pressure vessel 31 through the water supply pipe as feed water.

A plurality of main steam pipes 50 and a plurality of water supply pipes are arranged in the main steam pipe chamber 40 . The main steam pipe 50 is provided with main steam isolation valves 51a and 51b for isolating the environment inside and outside the reactor containment vessel 2 when the main steam pipe 50 is broken. The main steam isolation valve 51a is provided inside the reactor containment vessel 2, and the main steam isolation valve 51b is provided outside the reactor containment vessel 2 (main steam piping room 40). In addition, the main steam pipe 50 is provided with a safety valve (not shown) for releasing steam when the pressure inside the reactor pressure vessel 31 becomes high. It is then condensed in the suppression pool.

The RCIC steam pipe 61 is a steam guide pipe that guides part of the steam generated within the reactor pressure vessel 31 to the RCIC pump 63 . The RCIC steam pipe 61 is used to supply steam to the reactor when an abnormality such as breakage of the main steam pipe 50 occurs and the main steam isolation valves 51a and 51b are closed, making it impossible to supply water to the reactor through the water supply pipe. to the turbine that drives the RCIC pump 63 . That is, the RCIC steam pipe 61 is a pipe containing steam for driving the turbine for driving the RCIC pump. The steam that drives the RCIC pump 63 is led to the pressure suppression chamber 21 through the RCIC steam pipe 61 and condensed in the pressure suppression pool.

A heat exchanger (not shown), a CUW pump 64, and a reactor coolant cleanup device (not shown) are connected to the CUW pipe 62 to constitute a reactor coolant cleanup system (CUW: Reactor Water Clean-up System). do. The CUW piping 62 is a reactor water (coolant) guide piping that guides a portion of the reactor water in the reactor pressure vessel 31 to machines such as the heat exchanger, the CUW pump 64, and the reactor coolant purification system. The reactor coolant cleanup system is a system for removing impurities in reactor water (coolant) and maintaining water quality. A portion of high-temperature reactor water exceeding 280° C. is led from the reactor pressure vessel 31 to the CUW pipe 62 . The reactor water guided to the CUW piping 62 is cooled by the heat exchanger, then sent to the reactor coolant cleaning system through the CUW pump 64 and cleaned by the reactor coolant cleaning system. The purified coolant is returned to the reactor pressure vessel 31 after being heated by the heat exchanger.

As shown in FIGS. 1-3, the main steam tunnel building 7 is provided adjacent to the reactor building 1 . The main steam tunnel building 7 includes a main steam tunnel forming part 71 forming a main steam tunnel room 80 in which the main steam pipe 50 extending from the main steam pipe room 40 toward the turbine building 6 is arranged, and a main steam tunnel and a support frame 72 that rises from the building foundation 7 a and supports the main steam tunnel forming portion 71 . The main steam tunnel forming part 71 is connected to the frame wall 49 so as to maintain the airtightness of the main steam tunnel chamber 80 and the main steam pipe chamber 40 .

The main steam tunnel forming portion 71 forms a pipe accommodation portion 71a that forms a pipe accommodation chamber 81 that communicates with the main steam pipe chamber 40 and through which the main steam pipe 50 passes, and a flow path 82 that extends upward from the pipe accommodation chamber 81. a first flow path forming portion 71c, a first blowout panel 91 that closes the first steam outlet portion 71d provided in the first flow path forming portion 71c, and a turbine building 6 side (a piping housing portion 81 on the turbine building 6 side). and a partition wall 71 b that is provided at the end) and airtightly partitions the main steam tunnel chamber 80 and the main steam pipe chamber 40 . The main steam tunnel chamber 71 has a pipe housing chamber 81 communicating with the main steam pipe chamber 40 and a flow path 82 communicating with the pipe housing chamber 81 .

As shown in FIG. 1, the top of the first flow path forming portion 71c is set at a position lower than the top of the reactor building 1 (ceiling 22c). In this embodiment, the top portion of the first flow path forming portion 71c is set at a position lower than the operating floor 22a. The first steam outlet 71d is an opening that communicates between the inside of the main steam tunnel building 7 and the outside of the main steam tunnel building 7, and is provided below the operation floor 22a and above the ground level GL. be done.

In this embodiment, the first steam outlet portion 71d is formed so as to face the frame wall 49 of the reactor building 1 . The width of the first flow path forming portion 71c in the left-right direction in the drawing (the direction in which the reactor building 1 and the turbine building 6 are aligned) is shorter than the width in the left-right direction in the drawing of the pipe accommodating portion 71a. Further, the first flow path forming portion 71c is formed to extend upward from the turbine building 6 side end portion of the pipe accommodating portion 71a. For this reason, a step is formed by the left end portion of the pipe accommodating portion 71a in the drawing and the left wall of the first flow path forming portion 71c (the wall in which the first steam outlet portion 71d is formed) to form a first blowout panel. A space is formed between 91 and the side wall (body wall 49 ) of the reactor building 1 .

As shown in FIGS. 1 and 2, the partition wall 71b constitutes part of the frame wall of the main steam tunnel building 7 on the turbine building 6 side. The main steam pipe 50 is arranged so as to be led into the turbine building 6 through the partition wall 71b. A sealing member is provided between the through-hole of the partition wall 71b and the main steam pipe 50 so that the main steam tunnel chamber 80 and the main steam pipe chamber 40 are kept airtight. That is, the main steam tunnel room 80 and the turbine building 6 are not communicated with each other at the outer peripheral portion of the main steam pipe 50 .

As shown in FIGS. 1 to 3, the reactor building 1 includes a second flow path forming section 45 forming a flow path 45b communicating with the machine rooms 41 and 42, and a second flow path forming section 45 provided in the second flow path forming section 45. and a second blowout panel 92 closing off the steam outlet 45a. As shown in FIG. 1, the second flow path forming portion 45 extends upward from the reactor building foundation 1a. The top of the second flow path forming part 45 is set at a position lower than the top of the reactor building 1 (the ceiling 22c). In this embodiment, the top portion of the second flow path forming portion 45 is set at a position lower than the operating floor 22a.

The second flow path forming portion 45 is formed to protrude outward from the frame wall 48 of the reactor building 1 . The machine room 42 and the second flow path forming portion 45 are separated by a frame wall 48 of the reactor building 1 and communicate with each other through an opening 48 a of the frame wall 48 . The second steam outlet 45a is an opening that communicates between the inside of the reactor building 1 and the outside of the reactor building 1, and is provided below the operating floor 22a and above the ground level GL.

In the nuclear power plant 100 according to this embodiment, the main steam pipe chamber 40, the pipe housing chamber 81 of the main steam tunnel chamber 80, and the flow passage 82 form a first blowout flow passage B1. When the main steam pipe 50 in the main steam pipe chamber 40 breaks, steam is discharged to the outside of the building through the first blowout flow path B1 indicated by the dashed arrow in the figure. The first blowout flow path B1 guides the steam discharged from the broken portion of the main steam pipe 50 from the main steam pipe chamber 40 to the main steam tunnel chamber 80, and the first blowout flow passage B1 is directed to the main steam tunnel chamber 80 as the internal pressure of the main steam tunnel chamber 80 increases. By opening the blowout panel 91, it is a steam discharge flow path for discharging the steam in the main steam tunnel chamber 80 to the outside through the first steam outlet portion 71d. That is, the steam guided from the main steam pipe chamber 40 to the pipe housing chamber 81 flows in the first flow path forming portion 71c as an open space above the pipe housing chamber 81 (above the main steam pipe 50). It is guided to the path 82 and discharged to the outside of the building through the first steam outlet 71d.

In addition, the nuclear power plant 100 according to the present embodiment includes a machine room 41, a machine room 42, a communication passage (not shown) that communicates the machine room 41 and the machine room 42, an opening 48a of the frame wall 48, and a second A second blowout flow path B<b>2 is formed by the flow path 45 b in the flow path forming portion 45 . When the RCIC steam pipe 61 inside the machine room 41 is broken, the steam is discharged to the outside of the building through the second blowout flow path B2 indicated by the dashed arrow in the figure. The second blowout flow path B2 passes the steam discharged from the broken portion of the RCIC steam pipe 61 from the machine room 41 through the communication path, the machine room 42, and the opening 48a of the frame wall 48 to the second flow path forming part 45. The steam in the second flow path forming part 45 is directed to the flow path 45b, and the second blowout panel 92 is opened as the internal pressure of the second flow path forming part 45 rises. It is a steam discharge channel to be released.

Similarly, in this embodiment, when the CUW pipe 62 inside the machine room 42 is broken, the steam is discharged to the outside of the building through the second blowout flow path B2. That is, the second blowout channel B2 guides the steam emitted from the broken portion of the CUW pipe 62 from the machine room 42 through the opening 48a of the frame wall 48 to the channel 45b of the second channel forming portion 45, A steam discharge channel that releases the steam in the second channel forming part 45 to the outside through the second steam outlet part 45a by opening the second blowout panel 92 as the internal pressure of the second channel forming part 45 increases. also functions as

The second blowout channel B2 is an independent channel that does not communicate with the first blowout channel B1. In addition, the turbine building 6 is provided with a blowout panel 96 that is opened when a steam pipe is broken in the turbine building 6 and discharges steam to the outside of the building. The blowout passage in the turbine building 6 is an independent passage that does not communicate with the first blowout passage B1 and the second blowout passage B2.

The blowout panels 91, 92, 96 may be configured to be opened due to an increase in the internal pressure of the room in which the blowout panels 91, 92, 96 are installed, and are well-known clip type or rupture disk type blowout panels. is. By opening the blowout panels 91, 92, 96, the pressure inside the building can be released, and damage to the structures inside the building (the reactor containment vessel 2, etc.) can be prevented.

If the blow-out panels 91 and 92 are kept open for a long period of time after being opened due to the occurrence of an abnormal situation, there is a risk that radioactive substances inside the building will continue to leak out of the building. For this purpose, the blowout panels 91, 92 are provided with known closing devices for closing the steam outlets 71d, 45a after opening. As the closing device, for example, a device that can slide the shield door to the closed position so as to block the steam outlets 71d and 45a after the blowout panels 91 and 92 are opened can be adopted. In the present embodiment, since the steam outlets 71d and 45a can be closed by the closing device, the emergency gas treatment facility can be quickly activated to create a negative pressure in the building after the occurrence of an abnormal situation. Leakage of radioactive substances, etc. to the outside of the building can be suppressed.

According to the embodiment described above, the following effects are obtained.

(1) The nuclear power plant 100 includes a reactor building 1 that houses a reactor containment vessel 2 . The reactor building 1 includes a reactor pressure vessel 31 provided inside the reactor containment vessel 2, a main steam pipe 50 for guiding steam generated in the reactor pressure vessel 31 to the turbine building 6, and a reactor containment vessel. 2 and a pool (equipment temporary placement pool 24) provided above (directly above) the main steam pipe chamber 40 in which the main steam pipe 50 is arranged. The nuclear power plant 100 also includes a main steam tunnel forming section 71 that forms a main steam tunnel room 80 in which the main steam pipe 50 extending from the main steam pipe room 40 toward the turbine building 6 is arranged. The main steam tunnel forming portion 71 forms a pipe accommodation portion 71a that forms a pipe accommodation chamber 81 that communicates with the main steam pipe chamber 40 and through which the main steam pipe 50 passes, and a flow path 82 that extends upward from the pipe accommodation chamber 81. a first flow passage forming portion 71c, a first blowout panel 91 that closes the first steam outlet portion 71d provided in the first flow passage forming portion 71c, and a main steam tunnel chamber 80 that is provided on the turbine building 6 side and hermetically seals. It has a partition wall 71b that partitions into two. The main steam pipe 50 is arranged so as to be led into the turbine building 6 through the partition wall 71b. In the nuclear power plant 100, when the main steam pipe 50 in the main steam pipe room 40 breaks, the steam released from the broken portion of the main steam pipe 50 is directed from the main steam pipe room 40 to the main steam tunnel room 80. A first blowout flow path for discharging the steam in the main steam tunnel chamber 80 to the outside through the first steam outlet portion 71d by opening the first blowout panel 91 as the internal pressure of the main steam tunnel chamber 80 rises. B1 is formed.

According to this configuration, when the main steam pipe 50 inside the main steam pipe chamber 40 is broken, the pressure inside the building can be released by discharging the steam to the outside through the first blowout flow path B1. . Since the main steam tunnel room 80 and the turbine building 6 are partitioned by the partition wall 71 b , the steam released from the main steam pipe 50 is prevented from flowing into the turbine building 6 . Further, when an event such as a fire occurs in the reactor building 1, propagation of the event such as a fire into the turbine building 6 through the main steam tunnel room 80 is prevented. In other words, according to the present embodiment, the blowout flow is capable of releasing steam to the outside of the building when the pipe (main steam pipe 50) breaks, while suppressing adverse effects on machines of other systems (machines in the turbine building 6). A nuclear power plant 100 having a channel (first blowout channel B1) can be provided.

(2) The main steam pipe chamber 40 is a narrow space in which a plurality of main steam pipes 50, a plurality of feed water pipes, a main steam isolation valve 51b, etc. are arranged. Therefore, when a blowout panel and a closing device are provided in the main steam pipe room 40, there is a risk that their construction, maintenance and inspection will take time and effort. On the other hand, in the present embodiment, the first blowout panel 91 is provided in the first flow passage forming portion 71c extending upward from the pipe accommodating portion 71a, and the blowout panel is provided in the main steam pipe chamber 40. do not have. The internal space (flow path) of the first flow path forming portion 71 c is not a space for disposing the main steam pipe 50 , but can secure a wider work space than the main steam pipe chamber 40 . As described above, in the present embodiment, since the steam is discharged to the outside through the first steam outlet 71d provided at a position away from the main steam pipe 50, the blowout panel is provided in the main steam pipe chamber 40. Construction, maintenance and inspection of the blowout panel 91 can be easily performed compared to the case of providing the blowout panel 91 .

(3) If a plurality of blowout panels are provided on the flow path until the steam is discharged to the outside of the building when the main steam pipe 50 inside the main steam pipe room 40 breaks, the blowout panels close the flow path. Openings are provided for the number of blowout panels. On the other hand, in this embodiment, when the main steam pipe 50 of the main steam pipe chamber 40 is broken, the blowout panel provided on the first blowout flow path B1 until the steam is discharged to the outside of the building. is only one first blowout panel 91 . As a result, the number of openings can be reduced, and the building structural strength can be improved.

(4) The reactor building 1 is provided with an RCIC pump (machine) 63 and an RCIC steam pipe (guide pipe) 61 for guiding steam generated in the reactor pressure vessel 31 to the RCIC pump 63. 2, a CUW pump (machine) 64, and a CUW pipe (guide pipe) 62 for guiding the reactor water to the CUW pump 64 are provided. a second flow passage forming portion 45 forming a flow passage 45b communicating with the machine chambers 41 and 42; and a second blow outlet portion 45a provided in the second passage forming portion 45. and an out panel 92 . In the nuclear power plant 100, when the RCIC steam pipe 61 in the machine room 41 or the CUW pipe 62 in the machine room 42 breaks, the steam discharged from the broken part of the pipe is broken. From the machine chambers 41 and 42 to the flow path 45 b of the second flow path forming section 45 , the second flow path forming section 45 is opened by opening the second blowout panel 92 as the internal pressure of the second flow path forming section 45 increases. A second blowout flow path B2 is formed to release the steam inside to the outside through the second steam outlet portion 45a. The second blowout channel B2 is an independent channel that does not communicate with the first blowout channel B1.

In this way, the blowout passage (first blowout passage B1) that guides steam to the outside when the main steam pipe 50 is broken, and the steam to the outside when the RCIC steam pipe 61 and the CUW pipe 62 are broken. Since the blowout channel (the second blowout channel B2) is separated, it is possible to prevent the steam from flowing from one blowout channel to the other blowout channel. It is also possible to prevent an event such as a fire from propagating from one blowout channel to the other blowout channel. In other words, according to the present embodiment, the blower can release steam to the outside of the building when the pipe (main steam pipe 50) is broken while suppressing adverse effects on other system machines (RCIC pump 63, CUW pump 64, etc.). While suppressing adverse effects on the out flow path (first blowout flow path B1) and machines of other systems (main steam isolation valve 51b, etc.), when the piping (RCIC steam piping 61 and CUW piping 62) is broken, the steam is released to the building. It is possible to provide the nuclear power plant 100 having a blowout channel (second blowout channel B2) that can escape to the outside.

(5) The reactor building 1 has an operating floor 22 a provided above the reactor containment vessel 2 . The first steam outlet 71d and the second steam outlet 45a are provided below the operating floor 22a. Therefore, the risk of opening the blowout panels 91 and 92 due to the horizontal force and wind load during an earthquake can be reduced compared to the case where the blowout panels are provided above the operation floor 22a. Also, since the blowout panels 91 and 92 are installed near the ground level GL, maintenance and inspection are improved.

(6) The reactor building 1 has an operating floor 22a provided above the reactor containment vessel 2, an operating floor wall 22b rising from the operating floor 22a, and a ceiling 22c provided above the operating floor 22a. , an operating floor 22a, an operating floor wall 22b and a ceiling 22c define an operating floor area 22. As shown in FIG. The driving floor area 22 is not provided with a blowout panel. That is, in the present embodiment, the operating floor area 22 is not provided with a steam outlet closed by a blowout panel. Therefore, compared to the reactor building in which the steam outlet is provided in the operating floor area 22, the building structural strength can be improved.

The following modifications are also within the scope of the present invention, and it is also possible to combine the configurations shown in the modifications with the configurations described in the above embodiments, or to combine the configurations described in the following different modifications. is.

<Modification 1>
In the above-described embodiment, an example in which the first flow path forming portion 71c forms the flow path 82 extending upward from the pipe housing chamber 81 has been described, but the present invention is not limited to this. Modifications of the first flow path forming portion 71c will be described below.

<Modification 1-1>
FIG. 4 is similar to FIG. 2 and shows a modification of the first flow path forming portion 71c. As shown in FIG. 4 , in this modification, the first flow path forming portion 171 c forms a flow path 182 extending laterally from the pipe housing chamber 81 . A first steam outlet portion 171d is formed at the tip of the first flow path forming portion 171c, and a first blowout panel 191 is provided so as to block the first steam outlet portion 171d. That is, in this modified example, the main steam tunnel chamber 180 is formed by the pipe housing chamber 81 and the flow path 182 . According to such a modified example, it is possible to obtain the same effects as those of the above-described embodiment.

<Modification 1-2>
5 and 6 are similar to FIGS. 2 and 3, and show another modification of the first flow path forming portion 71c. As shown in FIG. 5, in this modified example, the first flow path forming portion 271c extends laterally from the pipe housing chamber 81, and further forms a flow path 282 extending upward at the side edge. do. Specifically, the first flow path forming portion 271c has a horizontal duct 271ca extending laterally from the pipe accommodating portion 71a and a vertical duct 271cb extending upward from the tip of the horizontal duct 271ca. A first steam outlet portion 271d is formed in the vertical duct 271cb, and a first blowout panel 291 is provided so as to block the first steam outlet portion 271d. That is, in this modified example, the main steam tunnel chamber 280 is formed by the pipe housing chamber 81 and the flow path 282 . According to such a modification, in addition to the same effect as the above embodiment, the height from the ground level GL to the first steam outlet portion 271d (first blowout panel 291) can be easily set. can be done.

<Modification 2>
In the above embodiment, an example in which the main steam tunnel building 7 is provided between the reactor building 1 and the turbine building 6 has been described, but the present invention is not limited to this. As shown in FIG. 7 , the main steam tunnel forming portion 71 forming the main steam tunnel chamber 80 and the support frame 72 supporting the main steam tunnel forming portion 71 may be formed integrally with the reactor building 1 . The support frame 72 is formed to stand up from the reactor building foundation 1a. According to such a modified example, it is possible to obtain the same effects as those of the above-described embodiment.

<Modification 3>
In the above embodiment, a plurality of pipes (main steam pipe 50, RCIC steam pipe 61, and CUW pipe 62) containing steam or reactor water generated in the reactor pressure vessel 31 are provided. a first blowout flow path B1 that guides the steam released from the broken portion of the first pipe (main steam pipe 50) to the first blowout panel 91 when the first pipe (main steam pipe 50) is broken; When the second pipe (RCIC steam pipe 61 and CUW pipe 62) among the plurality of pipes is broken, the steam released from the broken part of the second pipe (RCIC steam pipe 61 and CUW pipe 62) is blown out as a second blowout. Although the nuclear power plant 100 has been described in which the second blowout flow path B2 leading to the panel 92 is independently formed without communicating with each other, the present invention is not limited to this.

<Modification 3-1>
For example, the machine room 41 and the machine room 42 may not be communicated with each other through a communication path (not shown). FIG. 8 is similar to FIG. 3, and is a schematic cross-sectional plan view of a nuclear power generation facility 100 according to modification 3-1. The reactor building 1 according to this modification includes a flow path forming portion 445 that forms a flow path 445b that communicates with the machine room 41, a blowout panel 492 that closes the steam outlet portion 445a provided in the flow path forming portion 445, have That is, in this modification, when the RCIC steam pipe 61 is broken in the machine room 41, the blowout flow path that guides the steam released from the broken part of the RCIC steam pipe 61 to the blowout panel 492 and the machine room 42 A blowout flow path for guiding steam released from a broken portion of the CUW pipe 62 to the blowout panel 92 when the CUW pipe 62 is broken is formed independently without communicating with each other. According to such a modified example, in addition to the same effects as the above-described embodiment, the blowout flow path including the machine chamber 41 and the blowout flow path including the machine chamber 42 can be separated from each other when the pipe is broken. Steam spills into the system and propagation of events such as fires can be prevented.

<Modification 3-2>
Further, in the above-described embodiment, an example in which the main steam pipe room 40 and the machine room 41 are not communicated has been described, but the machine room 41 and the main steam pipe room 40 may be communicated. The machine room 41 and the machine room 42 may not be communicated with each other through a communication path (not shown). Depending on the arrangement, number, etc. of machines in each system, it is possible to appropriately provide a blowout flow channel for system separation and a blowout flow channel for non-system separation.

<Modification 4>
In the above embodiment, the blowout flow path when the main steam pipe 50, the RCIC steam pipe 61 and the CUW pipe 62 are broken has been described as the blowout flow channel when the high energy pipe is broken. The present invention may also be applied to a blowout flow path when a pipe breaks. High-energy piping refers to piping that contains steam and piping that contains reactor water exceeding 100° C., and indicates piping that releases steam from a fractured portion when broken.

Although the embodiments of the present invention have been described above, the above embodiments merely show a part of application examples of the present invention, and the technical scope of the present invention is not limited to the specific configurations of the above embodiments. do not have.

DESCRIPTION OF SYMBOLS 1... Reactor building, 2... Reactor containment vessel, 6... Turbine building, 7... Main steam tunnel building, 22... Operating floor area, 22a... Operating floor, 24... Pool, 25... Reactor well, 31... Reactor Pressure vessel 40 Main steam pipe chamber 41, 42 Machine room 45 Second flow path forming part 45a Second steam outlet 45b Flow path 48 Frame wall 48a Opening 49 Frame wall 50 Main steam pipe 51a, 51b Main steam isolation valve 61 RCIC steam pipe (guide pipe) 62 CUW pipe (guide pipe) 63 RCIC pump (machine) 64 CUW pump (Mechanical) 71 Main steam tunnel forming part 71a Pipe accommodating part 71b Partition wall 71c First flow path forming part 71d First steam outlet 80 Main steam tunnel chamber 81 Piping Storage chamber 82 Flow path 91 First blowout panel 92 Second blowout panel 171c First flow path forming portion 171d First steam outlet 180 Main steam tunnel chamber 182 Flow path 191 First blowout panel 271c First flow path forming portion 271ca Horizontal duct 271cb Vertical duct 271d First steam outlet 280 Main steam tunnel chamber 282 Flow path 291... First blow-out panel, 445... Flow path forming part, 445a... Steam outlet part, 445b... Flow path, 492... Blow-out panel, B1... First blow-out flow path, B2... Second blow-out flow path, GL: ground level

Claims (4)

A nuclear power plant comprising a reactor building housing a reactor containment vessel,
The reactor building includes a reactor pressure vessel provided inside the reactor containment vessel, a main steam pipe for guiding steam generated in the reactor pressure vessel to the turbine building, and a a main steam pipe room in which the main steam pipe is arranged, and a pool provided above the main steam pipe room,
a main steam tunnel forming part forming a main steam tunnel room in which the main steam pipe extending from the main steam pipe room toward the turbine building is disposed;
The main steam tunnel forming part forms a pipe housing part communicating with the main steam pipe chamber and forming a pipe housing chamber through which the main steam pipe passes, and a flow path extending upward or sideways from the pipe housing chamber. a first flow passage forming portion that closes the first steam outlet provided in the first flow passage forming portion; and a partition that is provided on the turbine building side and airtightly partitions the main steam tunnel chamber. having a wall and
the main steam pipe is arranged so as to be led into the turbine building through the partition wall;
In the nuclear power plant, when the main steam pipe in the main steam pipe room is broken, the steam released from the broken portion of the main steam pipe is guided from the main steam pipe room to the main steam tunnel room. a first blowout passage for discharging steam in the main steam tunnel chamber to the outside through the first steam outlet is formed by opening the first blowout panel as the internal pressure of the main steam tunnel chamber rises; is,
The reactor building is
a machine room provided on the side of the reactor containment vessel, in which a guide pipe for guiding steam or reactor water generated in the machine and the reactor pressure vessel to the machine is arranged;
a second flow path forming portion that forms a flow path that communicates with the machine chamber;
a second blowout panel that closes the second steam outlet provided in the second flow path forming section;
In the nuclear power plant, when the guide pipe in the machine room is broken, the steam released from the broken part of the guide pipe is guided from the machine room to the flow channel of the second flow channel forming part, A second blowout flow that releases the steam in the second flow path forming portion to the outside through the second steam outlet portion by opening the second blowout panel as the internal pressure of the second flow path forming portion rises. a path is formed,
The second blowout channel is an independent channel that does not communicate with the first blowout channel,
Nuclear power plant. In the nuclear power plant according to claim 1 ,
The reactor building has an operating floor provided above the reactor containment vessel,
The first steam outlet and the second steam outlet are provided below the operating floor,
Nuclear power plant. In the nuclear power plant according to claim 1,
The reactor building has an operating floor provided above the reactor containment vessel, an operating floor wall rising from the operating floor, and a ceiling provided above the operating floor. an operating floor area is defined by the operating floor wall and the ceiling;
The driving floor area is not provided with a blowout panel,
Nuclear power plant. A nuclear power plant comprising a reactor building housing a reactor containment vessel,
A reactor pressure vessel is provided inside the reactor containment vessel,
Having a plurality of pipes containing steam or reactor water generated in the reactor pressure vessel,
a first blowout flow path for guiding steam released from a broken portion of the first pipe to a first blowout panel when the first pipe among the plurality of pipes is broken; A second blowout flow path for guiding the steam released from the broken portion of the second pipe to the second blowout panel when the two pipes are broken is formed independently without communicating with each other. ,
Nuclear power plant.

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