JP2899384B2 - Reactor emergency condensing device and its installation device - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a reactor emergency condensing device for condensing steam in a nuclear reactor in an emergency and cooling the reactor, and an installation device therefor. About.

(Prior Art) A conventional nuclear reactor condensing apparatus will be described with reference to FIG. 8 and FIG. FIG. 8 is a diagram showing a piping flow path system in which the conventional reactor condensing device 6 is incorporated in the reactor containment vessel 1. In FIG. 8, a reactor pressure vessel 2 is arranged in a reactor containment vessel 1, and an inlet pipe 3 connected to the reactor pressure vessel 2 is connected to a reactor via a first inlet valve 4 and a second inlet valve 5. It is connected to a furnace emergency condensing device 6. The other end of the outlet pipe 7 connected to the reactor emergency condensing device 6 is connected to the reactor pressure vessel 2 via a first outlet valve 8 and a second outlet valve 9.

FIG. 9 is a longitudinal sectional view partially showing a side view of a conventional horizontal U-tube type reactor emergency condenser 6. The conventional reactor emergency condensing device 6 includes a cylindrical steam chamber 17 and a water chamber 18 projecting to the outside of a lower portion of a steel tank 15, and a steam chamber 17 and a water chamber 18.
And a plurality of U-shaped heat transfer tubes 24 connected to the tube sheet 19 and communicating with the steam chamber 17 and the water chamber 18, and a lid attached to the steam chamber 17 and the water chamber 18. 20 and tank 15
It comprises a steam vent pipe 16 attached to the upper part, an inlet pipe 3 connected to a steam chamber 17, and an outlet pipe 7 connected to a water chamber 18.

During normal operation of the reactor, the first outlet valve 8 is closed, and the first inlet valve 4, the second inlet valve 5, and the second inlet valve 9 are open.

Main steam pipe (not shown) connected to reactor pressure vessel 2
When the reactor is isolated, by opening the first outlet valve 8, the flow path returning from the reactor pressure vessel 2 to the reactor pressure vessel 2 via the inlet pipe 3, the reactor emergency condensing device 6, and the outlet pipe 7 is formed. It is formed. The steam in the reactor pressure vessel 2 flows from the inlet pipe 3 into the steam chamber 17, further flows into the heat transfer pipe 24, exchanges heat with water in the tank 15, and is condensed. The condensed water flows into the water chamber 18 and returns to the reactor pressure vessel 2 via the outlet pipe 7. The water in the tank 15 is heated on the surface of the heat transfer tube 24 and boils. The generated steam is released from the steam discharge pipe 16 to the outside.

In the heat transfer tube inspection at the time of maintenance and inspection, the lid 20 attached to the steam chamber 17 and the water chamber 18 is removed, and an eddy current flaw detection test and the like are performed from the inside of the U-shaped heat transfer tube 24 connected to the tube sheet 19.

(Problems to be Solved by the Invention) Currently, in a nuclear power plant, there is a demand for a device having a simple structure and improved reliability by reducing the number of power devices such as pumps. Thus, the above-mentioned reactor emergency condensing apparatus, which can cool the reactor without using a pump or the like, is increasing in importance.

Therefore, it has been considered to install a plurality of reactor condensing units in a large-sized concrete pool so that heat can be removed for a longer time. Conventional horizontal U
The area required for installation is large in the U-tube type reactor emergency condensing unit, the layout restrictions are large when multiple units are installed in the pool, and the drainage of condensed water is poor in the horizontal tube, There is a problem that the condensation performance is lower than that of the vertical tube. For this reason, a small-sized reactor condensing apparatus for a reactor having a vertical heat transfer tube group, a steam chamber at the upper part thereof, a water chamber at the lower part thereof, and condensing in the heat transfer pipes has been considered.
However, in this type of condensing equipment for a nuclear reactor, when the pool water boiling outside the pipe rises, it is hindered by the lower surface of the steam chamber, weakens the ascending flow, and increases the weight of the steam chamber, which is unfavorable in terms of earthquake resistance. is there. In addition, for eddy current testing of heat transfer tubes, it is necessary to remove the lid of the steam chamber. Furthermore, since the outside of the steam chamber is always filled with water, there is a problem that condensation occurs during normal operation and unnecessary heat radiation occurs.

Also, when performing maintenance and inspection work on the reactor emergency condenser, it is necessary to discharge all of the large amount of pool water in the condenser pool before performing maintenance and inspection work. There is a problem that a large amount of pool water has to be supplied to the pool again after the work, and there is a problem that a large amount of time is required for maintenance and inspection work.

The present invention has been made to solve the above problems,
It is an object of the present invention to provide a reactor emergency condensing apparatus which has high condensing performance, has no problem such as heat radiation, and is excellent in maintainability.

The present invention also provides a reactor emergency condensing device which can reduce the work time required for maintenance and inspection of a reactor emergency condensing device by limiting the drainage range without discharging the entire pool water in a large condensing device pool. It is an object of the present invention to provide a device installation device.

[Structure of the Invention] (Means for Solving the Problems) The invention of claim 1 is directed to a vertical cylindrical trunk installed in a reactor emergency condensing pool provided above a reactor containment vessel; A pair of tube sheets connected to the upper and lower ends of the trunk, and a plurality of vertical heat transfer tubes opened and connected to the pair of tube sheets,
One end is connected to the upper or upper tube sheet of the trunk, and the other end is connected to a reactor pressure vessel to which a pressure reducing pipe is connected via a pressure reducing valve, and an inlet pipe through which steam from the reactor pressure vessel flows. One end is connected to the lower or lower tube sheet of the shell, the other end is connected to an outlet pipe through which condensed water flows into the reactor pressure vessel, and one end is connected to the inside of the shell at a position higher than the outlet pipe. A vent pipe connected at the other end to a pressure suppression pool provided below the reactor containment vessel to open and discharge a non-condensable gas; a bottom pipe connected to the body and a bottom pipe of the pool; And a plurality of legs extending downward so as to form a space between the plate and the board.

According to a second aspect of the present invention, the reactor emergency condensing device according to the first aspect is installed in a condensing pool, the bottom plate through which the inlet pipe, the outlet pipe, and the vent pipe penetrate, and the reactor standing upright from the bottom plate. An outer shroud surrounding the entire emergency condenser, a skirt provided inside the outer shroud and having a lower end opened, and a pool water inlet pipe at a position lower than a mounting position of the skirt provided on the outer shroud; A drain pipe connected to the bottom plate.

(Operation) In the invention of claim 1, when the main steam pipe connected to the reactor pressure vessel is isolated, steam flows from the reactor pressure vessel into the cylindrical body through the first pipe of the reactor emergency condensing device. The heat is exchanged and condensed outside the plurality of heat transfer tubes, and is returned to the reactor pressure vessel by the second pipe. The pool water around the emergency condenser is guided from the lower tube sheet into the heat transfer tubes, heated and boiled, and flows upward from the upper tube sheet. This allows the reactor steam to condense and transfer heat to the pool water, thereby safely cooling the reactor.

According to the second aspect of the present invention, it is not necessary to discharge all of the pool water in the condenser pool when installing and maintaining and inspecting the reactor condensing apparatus according to the first aspect in a large-sized condensation pool. It is only necessary to discharge the pool water inside the tank, or at the time of inflow, only the amount of water of the inner volume of the shroud should be introduced. Can be shortened.

(Embodiment) A first embodiment of a reactor emergency condensing apparatus according to the present invention will be described with reference to FIGS. 1 to 4.

FIG. 1 shows a piping flow system in which a reactor emergency condensing device 6a is incorporated in a reactor containment vessel 1 according to a first embodiment. The vapor phase portion 2a of the reactor pressure vessel 2 installed in the reactor containment vessel is connected to the reactor emergency condensing device 6a via the inlet pipe 3, and the reactor emergency condensing device 6a is connected via the outlet pipe 7. The vent pipe 10 is connected to the pressure suppression pool 27 via the vent valve 11.

A pressure reducing pipe 13 is connected to the vapor phase portion 2a of the reactor pressure vessel 2, and a pressure reducing valve 14 is connected to the other of the pipes.
The discharge side pressure reducing pipe 13 of 14 is open to the space inside the reactor containment vessel 1.

FIG. 2 is a reactor emergency condensing apparatus according to the first embodiment.
FIG. 6B is an outline drawing showing an overall outline of 6a. The reactor emergency condensing device 6a includes a circular and horizontal upper tube sheet 21, a circular and horizontal lower tube sheet 22, and a vertical cylinder connected to the entire periphery of the upper and lower tube sheets 21 and 22. Body 23, upper tube sheet 21 and lower tube sheet
A plurality of vertical heat transfer tubes 24 connected to 22 and open at both ends,
A leg 25 attached to the outer periphery of a body 23 capable of providing a gap between the lower tube sheet 22 and the installation floor surface with a gap therebetween, and an upper tube sheet 21
, An outlet pipe 7 connected to the body 23, a vent pipe 10, and a heat insulating material 26 attached to the outer periphery of the inlet pipe 3. The outlet pipe 7 is connected to the lowermost portion of the body 23, and the vent pipe 10 is connected to a position higher than the outlet pipe 7 and symmetrically with the inlet pipe 3 with respect to the center line of the cylinder of the body 23.

FIG. 3 is a view showing a vertical cross section of the reactor emergency condensing device 6a in the first embodiment shown in FIG. The heat transfer tubes 24 are connected so as to open through the upper tube sheet 21 and the lower tube sheet 22. The inlet pipe 3 forms a U-shaped pipe.

FIG. 4 is a longitudinal sectional view showing an installation device of the reactor emergency condensing device of the first embodiment in FIGS. 2 and 3.

The reactor emergency condenser 6a is provided with a circular copper bottom plate 32 on a part of the concrete slab 31 forming the bottom of the condenser pool 30 filled with water, and the reactor emergency condenser 6a is placed on the bottom plate 32. Is installed.

A cylindrical outer shroud 33 having a cylindrical upper end and a lower end than the water surface of the condenser pool 30 is installed around the reactor emergency condenser 6a. The pool water inlet valve 34 is connected to the outer shroud 33 at a height close to the upper surface of the concrete slab 31 via a pool water inlet pipe 35. Also skirt 36
Is connected to the inner surface of the outer shroud 33 at a position higher than the opening of the pool water inlet pipe 35, and the lower end of the skirt 36 is set to a height near the lower surface of the reactor emergency condensing device 6. A drain valve 38 is connected to the bottom plate 32 via a drain pipe 37. At the upper end of the outer shroud 33, an outer shroud 33 and a cylindrical weir 39 are installed so as to be detachable.

Next, the reactor condensing unit 6a configured as described above
The operation of the installation device will be described.

When the main steam pipe connected to the reactor pressure vessel is isolated, the reactor emergency condensing device 6a in the present embodiment condenses steam generated in the reactor pressure vessel and cools the reactor pressure vessel. . In the unlikely event that an accident such as a pipe break occurs in the primary containment vessel 1, the primary containment vessel 1
The inside of the reactor is condensed, and the containment vessel 1 is cooled.

During normal operation of the reactor, the first inlet valve 4, the second inlet valve 5,
The first outlet valve 8 is kept open, and the second outlet valve 9 and vent valve 11 are kept closed. Reactor emergency condenser
The inside of 6a, the outlet pipe 7, and the inside of the vent pipe 10 are filled with water in advance, and the heat transfer tube 24, the body 23, and the upper tube sheet 21 are kept out of contact with steam.

From the inverted U-shaped pipe section of the inlet pipe 3 to the reactor pressure vessel 2
The piping up to is filled with steam, but heat exchange with the pool water is suppressed as much as possible by the surrounding heat insulating material 26. The weir 39 above the outer shroud 33 is in a detached state, and the pool water inlet valve 34 is in a closed state.

When the main steam pipe (not shown) of the reactor is isolated, the second outlet valve is opened immediately, so that the condensed water in the reactor emergency condenser 6a flows into the reactor through the outlet pipe 7 by gravity. . As a result, steam starts flowing from the reactor pressure vessel 2 through the inlet pipe 3 into the reactor emergency condensing device 6a. The steam flowing into the reactor emergency condensing unit 6a is
Heat exchange with the pool water through the heat exchanger, condenses on the outer peripheral surface of the heat transfer tube 24, the condensed water falls to the bottom of the reactor emergency condensing device 6a, and continuously flows to the reactor pressure vessel 2 through the outlet pipe 7. Will be returned. Since the reactor emergency condensing device 6a is installed at a position higher than the reactor pressure vessel 2, a natural circulation force is generated by the action of gravity due to a difference in density between steam in the inlet pipe 3 and condensed water in the outlet pipe 7. Then, steam is continuously flown into the reactor emergency condensing device 6a to perform condensation.

On the other hand, the pool water heated on the inner surface of the heat transfer tube 24 boils and enters a two-phase flow state, so that the density difference between the pool water around the reactor emergency condensing device 6a and the water inside the heat transfer tube 24 is reduced. And an upward flow occurs. As a result, the pool water flows from the pool water inlet valve 34, is guided along the skirt 36 to the lower part of the reactor emergency condensing device 6a, flows into the heat transfer tube 24, is heated and boiled, and rises upward from the heat transfer tube 24. leak.

 Next, the operation in the event of an accident will be described.

In the event that a pipe break occurs in the reactor containment vessel 1, the pressure reducing valve 14 is opened to release the steam in the reactor pressure vessel 2, the pressure is reduced, and the gravity drop type emergency core cooling device ( (Not shown), the core is cooled. After the reactor pressure vessel 2 is sufficiently depressurized, the second outlet valve 9 is opened to allow the steam to flow through the inlet pipe 3 to the reactor emergency condensing device in the same manner as the above-described cooling when the reactor main steam pipe is isolated. 6a
And condensed, and the condensed water is returned to the reactor through the outlet pipe 7.

As the steam in the reactor pressure vessel 2 is condensed, the pressure decreases, and the steam initially discharged into the reactor containment vessel 1 flows back through the pressure reducing valve 14, and the steam in the reactor containment vessel 1 also condenses. Is done. When the non-condensable gas in the reactor containment vessel 1 collects around the heat transfer tubes 24 and the heat transfer performance decreases, the pressure in the reactor pressure vessel 2 increases temporarily. Then, by opening the vent valve 11, the non-condensable gas is pushed out into the pressure suppression pool, and the condensation is started again. Reactor emergency condensing unit for vent pipe 10 even if vent valve 11 is open
Since the opening of the outlet pipe 7 is located at a position lower than the opening in 6a, the pipe is preferentially returned to the reactor from the outlet pipe 7 for condensation.

Next, maintenance and inspection will be described. In the periodic inspection, a weir 39 is attached to the upper part of the outer shroud 33, the pool water inlet valve 34 is closed, the drain valve 38 is opened, and the pool water in the outer shroud 33 is drained from the drain pipe 37. As a result, it is possible for an operator to approach the reactor emergency condensing device 6a and perform an inspection. In this state, an element can be inserted into the tube to perform an overcurrent flaw detection test.

In the event that repair becomes necessary, the legs 25 can be removed from the pool by removing the fixing of the legs 25 and removing the flanges of the connection pipes.

The reactor emergency condensing apparatus according to this embodiment has the following effects.

Since the heat transfer tube is provided vertically and the condensed water drops and is eliminated by gravity most quickly, the liquid film formed on the surface of the heat transfer tube becomes thin, and a high condensation ability is obtained.

Since it is a vertical pipe, there is no obstacle to the rise of the pool water, a high circulation flow rate of the pool water is obtained, and a high heat transfer performance is obtained.

In order to prevent rapid condensation at startup, the inlet valve must always be open during normal operation, but in this embodiment, since the inlet pipe is connected to the upper surface, the inside is filled with water during normal operation, The structure is such that heat transfer tubes do not come into contact with steam.

Since the inlet pipe is covered with a heat insulating material, heat can be prevented from being released due to unnecessary condensation during normal operation. Therefore,
There is no problem such as a decrease in the efficiency of the reactor and an unnecessary rise in the temperature of the pool water.

In the inspection, unlike a normal heat exchanger, the structure does not have a water chamber.Therefore, even in the turbulent flow flaw detection test of the heat transfer tube, it is not necessary to remove the lid of the water chamber, etc. Can be inserted. For this reason, a very large maintenance work can be reduced, and an even greater effect is achieved in reducing the exposure of the workers.

Because of the structure in which the reactor steam flows into the shell side, in the above-mentioned operation where inspection is performed from the tube side, the workers do not face directly to the highly radioactive shell side, and thus reduce the exposure of workers. Greater effects can be expected.

By installing an external shroud in the pool water and discharging only the water in the external shroud without draining the entire pool water, the time required for inspection and maintenance is reduced.

There is no need to have a heavy steam chamber at the top,
It is also very advantageous for earthquake resistance.

Since the heat transfer tube and the shell are always in the same condition, a difference in thermal expansion is unlikely to occur, and there is no need to generate an excessive stress and a special design for preventing it.

A second embodiment of the reactor emergency condensing apparatus according to the present invention will be described with reference to FIGS.

FIG. 5 is a view showing a pipe flow system incorporating a reactor emergency condensing device 6b according to a second embodiment of the present invention. An inlet pipe 3 opened into the containment vessel 1 is connected to a reactor emergency condenser 6b via an inlet valve 4. Further, an outlet pipe 7 is connected from the reactor emergency condensing device 6b through an outlet valve 8 so as to open into the suppression pool 13.

FIG. 6 is a longitudinal sectional view of a second embodiment of the present invention. The structure of the upper tube sheet 21, the lower tube sheet 22, the body 23, the heat transfer tubes 24, and the legs 25 is the same as in the first embodiment. The inlet pipe 3 is attached to and connected to the upper part of the body 23. The outlet pipe 7 is connected to the lowermost portion at a position symmetrical to the inlet pipe 3 with respect to the center line of the cylinder of the body 23. Other components such as an external shroud are the same as those in the first embodiment.

Next, the operation of the second embodiment will be described. The reactor emergency condensing device 6b according to the present embodiment condenses the vapor in the reactor containment vessel 1 in the event of an accident such as a pipe break in the containment vessel 1, Cool 1

During normal operation of the reactor, the inlet valve 4 is kept open and the outlet valve 8 is kept closed. In the event of an accident, the pressure reducing valve 14 is opened, the pressure is reduced, and the core is cooled by a gravity drop type emergency core cooling device (not shown). After that, the steam released into the reactor containment vessel 1 by opening the outlet valve 8 is released to the suppression pool 13 through the reactor condensing device 6b. At this time, heat exchange is performed with the pool water via the heat transfer tube 24, and steam is condensed. The condensed water is discharged to the suppression pool through the outlet pipe 7. In this case, the operation on the pool water side is the same as in the first embodiment.

The same applies to the maintenance and inspection as in the first embodiment.

The reactor condensing device 6b in this embodiment has exactly the same effects as the first embodiment in terms of high condensing performance and excellent maintenance and inspection. Further, since this embodiment is used for cooling the containment vessel, the design pressure is reduced to about one-twentieth as compared with the first embodiment also used for cooling when the reactor is isolated. The thickness of the equipment piping is greatly reduced. In the actual design, the heat transfer area required for cooling the containment vessel in the event of an accident is larger than the heat transfer area required for cooling when the reactor is isolated. For this reason, the reactor emergency condenser of the first embodiment is installed in the number required for cooling during reactor isolation, and the reactor emergency condenser of the second embodiment is cooled for cooling the containment vessel. The combination of the shortage of the number of bases enables a more economical design.

In the second embodiment, as in the first embodiment, a configuration in which the outlet pipe is connected to the reactor pressure vessel and the vent pipe is connected to the pressure suppression pool is also conceivable.

Next, a third embodiment of the reactor emergency condensing device 6c according to the present invention will be described with reference to FIG. FIG. 7 is a longitudinal sectional view showing the third embodiment. The torso 23 has a cylindrical shape, and a concentric circular upper flange 23 that protrudes outward at an upper end.
a, and has a concentric circular lower flange 23b protruding inward at the lower end. Upper tube sheet 21 is upper flange 23a of body 23
The lower tube sheet 22 has a diameter smaller than the inner diameter of the body 23 and has a circular shape sized to match the lower flange 23b of the body 23. The upper flange of the body 23 and the upper tube sheet and the lower flange of the body 23 and the lower tube sheet are joined by bolts (not shown). Other, legs 25, heat transfer tube 2
4, the configuration of the inlet pipe 3, the outlet pipe 7, the vent pipe 10, the heat insulating material 26, and the configuration of the pipe flow system are the same as those in the first embodiment.

Next, the operation of the reactor emergency condensing device 6c according to the present embodiment will be described. The operations during the normal operation of the reactor, during the isolation of the reactor, and at the time of an accident are the same as those in the first embodiment.

In the present embodiment, when maintenance of the inside of the body 23 is required during maintenance and inspection, the upper tube sheet 21 and the upper flange 23 of the body 23 are required.
The upper tube sheet 21, the lower tube sheet 22 and the heat transfer tube 24 can be pulled out integrally by removing the bolts of a and the bolts of the lower tube sheet 22 and the lower flange 2b of the body 23.

The reactor condensing device 6c in this embodiment has the same effects as the first embodiment in terms of high condensing performance and excellent maintenance and inspection. Furthermore, since maintenance and inspection of the inside of the body and the outer surface of the pipe are also possible, higher maintenance and inspection performance can be obtained.

It is also possible to apply the reactor emergency condensing apparatus characterized by the flange connection according to the present embodiment to the second embodiment.

[Effects of the Invention] The present invention has the following effects.

Suitable for installation in a large-capacity pool because it has a structure that can stand on the bottom of the pool with legs and can be cooled by the natural environment of the surrounding pool water, and it is easy to take out from the pool. And is very effective in obtaining a longer heat removal capability.

Since the heat transfer tubes are installed vertically, the condensed water on the surface of the heat transfer tubes descends due to its own weight, making it the structure that is most likely to be eliminated, making it possible to thin the liquid film of the condensed water suspended on the surface of the heat transfer tubes. is there. Since the liquid film has a large thermal resistance, the thinner the liquid film, the higher the heat transfer coefficient can be obtained in condensing heat transfer.However, the condensing unit for an emergency reactor according to the present invention has high condensing performance due to the thinnest liquid film structure. Can be

The pool water is heated inside the heat transfer tube and boils up,
Since the heat transfer tubes are vertical and there are no structures at the top that obstruct the ascending flow, a strong ascending flow occurs due to the same effect as the two-phase flow inside the heat transfer tubes and the collision due to the difference in the density of pool water in the surrounding area. Is generated, a high flow rate in the heat transfer tube is obtained, and a high heat transfer coefficient is obtained. Therefore, it is possible to obtain a more compact, high-performance emergency reactor condensing device.

In a normal heat exchanger or condenser, there is a water chamber or a steam chamber on the heat transfer tube side, and in the eddy current flaw detection test of the heat transfer tube or the like, it is necessary to open a lid of the water chamber or the steam chamber. On the other hand, in the present invention, the structure is submerged in the pool,
Furthermore, since the pool water flows inside the heat transfer tubes, there is no steam room or water room.During maintenance, remove any bolts on the water room and steam room lids and remove any work. In addition, inspection work inside the heat transfer tube is possible, and maintenance work is greatly reduced.

There is no need for a heavy steam chamber at the top, and it is very effective for earthquake resistance.

Further, since the heat transfer tube and the body always have the same temperature condition, it is possible to realize a simple structure without generating excessive stress due to a difference in thermal expansion and special design for preventing the stress.

Since the furnace steam containing radioactivity passes through the shell side, it is very effective in reducing the exposure in the eddy current flaw test conducted from the inside of the heat transfer tube without the worker facing the inner surface of the shell side.

According to the installation device of the reactor emergency condensing device, the provision of the external shroud can limit the outflow and inflow amount of the pool water, so that the maintenance and inspection work time can be greatly reduced.

As described above, according to the present invention, there is a great effect on the degree of freedom in installation layout, heat transfer performance, maintenance and inspection, seismic resistance, etc., and a great effect on the construction of a simplified nuclear power plant in the future. Can be expected.

[Brief description of the drawings]

FIG. 1 is a piping flow diagram incorporating a first embodiment of a nuclear reactor condensing apparatus according to the present invention, and FIG. 2 is a first embodiment of a nuclear reactor condensing apparatus according to the present invention. Perspective view,
FIG. 3 is a longitudinal sectional view of FIG. 2, FIG. 4 is a longitudinal sectional view for explaining an embodiment of an installation apparatus of a reactor emergency condensing apparatus according to the present invention, and FIG. FIG. 6 is a longitudinal sectional view showing a second embodiment of the reactor emergency condensing apparatus according to the present invention, and FIG. Fig. 8 is a longitudinal sectional view showing a third embodiment of the reactor emergency condensing apparatus according to the present invention, Fig. 8 is a piping flow diagram incorporating a conventional reactor emergency condensing apparatus, and Fig. 9 is a conventional atomic condensing apparatus. It is a longitudinal section showing a furnace emergency condensing device. DESCRIPTION OF SYMBOLS 1 ... Containment vessel, 2 ... Reactor pressure vessel, 3 ... Inlet piping, 4 ... First inlet valve, 5 ... Second inlet valve, 6,6a, 6b, 6c ... Reactor emergency condensing unit, 7 ... Outlet piping, 8 ... first outlet valve,
9: Second outlet valve, 10: Vent piping, 11: Vent valve, 12 ...
Reactor emergency condensing pool, 13 ... pressure reducing pipe, 14 ... pressure reducing valve,
15… Tank, 16… Steam release pipe, 17… Steam room, 18… Water room,
19 ... tube sheet, 20 ... lid, 21 ... upper tube sheet, 22 ... lower tube sheet, 23 ...
Body, 24: Heat transfer tube, 25: Leg, 26: Thermal insulation, 27: Suppression pool, 28, 29: Pool water, 30: Condenser pool, 31: Concrete slab, 32: Bottom plate, 33: External shroud, 34
... Pool water inlet valve, 35 ... Pool water inlet pipe, 36 ... Skirt, 37 ... Drain pipe, 38 ... Drain valve, 39 ... Weir.

Claims (2)

(57) [Claims] 1. A vertical cylindrical body installed in a reactor emergency condensing pool provided above a reactor containment vessel, a pair of tube sheets connected to upper and lower ends of the body, and a pair of tube sheets. A plurality of vertical heat transfer tubes opened and connected to the tube plate of the reactor pressure vessel having one end connected to the upper or upper tube sheet of the shell and the other end connected to a pressure reducing pipe via a pressure reducing valve. An inlet pipe for connecting and inflowing steam from the reactor pressure vessel, and an outlet pipe having one end connected to the lower or lower tube sheet of the shell and the other end flowing condensed water into the reactor pressure vessel. A vent connected at one end to the inside of the body at a position higher than the outlet pipe, and connected at the other end to a pressure suppression pool provided below the reactor containment vessel to open and discharge a non-condensable gas. A space is formed between the tube, the bottom surface of the pool connected to the body, and the lower tube sheet. A plurality of legs and the reactor emergency condenser, characterized by comprising the extending downwardly as. 2. The reactor emergency condensing apparatus according to claim 1, wherein said inlet pipe, said outlet pipe, and said vent pipe are provided in a condensing pool, and a bottom plate penetrates through said bottom plate. An outer shroud surrounding the entire condenser, a skirt provided inside the outer shroud and having a lower end opened, a pool water inlet pipe located below a mounting position of the skirt provided on the outer shroud, and the bottom plate; And a drain pipe connected to the reactor.