JP2013152150A - Nuclear reactor residual heat removal device - Google Patents

Abstract

PROBLEM TO BE SOLVED: To secure the soundness of a nuclear reactor coolant boundary by surely and efficiently cooling a cover gas area and lowering the temperature and pressure of the cover gas area.SOLUTION: A nuclear reactor residual heat removal device having a reactor vessel 5 holding liquid metal 3 inside, a cover gas area 4 provided at an upper part of the reactor vessel 5, and a radiation detection device 24 for detecting a radiation of the cover gas area 4 includes a discharge pipeline 19 arranged in the cover gas area 4 and provided with a discharge port 19a for discharging the liquid metal 3 into the cover gas area, and a suction pipeline 21 for sucking the liquid metal 3 in the reactor vessel 5 and supplying the liquid metal to the discharge pipeline 19.

Description

  The present invention relates to a nuclear power plant, and more particularly to an apparatus for removing residual heat from a liquid metal cooled nuclear reactor.

  An outline of a conventional liquid metal cooled nuclear reactor will be described with reference to FIG. In the liquid metal cooled nuclear reactor 1, the nuclear fuel core 2 is disposed in a reactor vessel 5 that holds a liquid metal 3 such as sodium as a coolant, and a shielding plug 18 is installed above the reactor vessel 5. The in-furnace upper structural member 9 including a control rod driving mechanism and the like is disposed through the 18.

  A cover gas region 4 filled with an inert gas such as argon gas is provided in the upper part of the reactor vessel 5, and the reactor vessel 5 is stored in a guard vessel 7 through a gap 6 filled with nitrogen gas or the like. The vessel 7 is stored in a silo formed by a steel liner 15 and a concrete structure 16 that are dug underground.

  In such a liquid metal cooled nuclear reactor 1, there is a case where the nuclear fission reaction of the fuel is stopped in order to cope with an emergency situation during the operation of the nuclear reactor or to perform maintenance and inspection. In order to continue to be generated from the core, it is necessary to remove the residual decay heat generated from the liquid metal cooled nuclear reactor 1.

  The residual decay heat generated from the liquid metal cooled nuclear reactor 1 is transmitted from the reactor vessel 5 to the guard vessel 7 by heat radiation, and the heat from the guard vessel 7 is generated by the steel liner 15 and the concrete structure 16 installed outside. Radiated into the formed silo.

  In the conventional liquid metal cooled nuclear reactor 1, in order to remove the heat of the guard vessel 7, the collector 10 that partitions the annular space 13 existing between the guard vessel 7 and the silo, and the downward flow of air formed thereby. A reactor vessel auxiliary cooling system (RVACS) comprising a passage 11, an air rising channel 12, an air intake 14 for taking in air, and a duct 17 for releasing superheated air; Thereby, residual decay heat generated from the liquid metal cooled nuclear reactor 1 is removed (Patent Document 1).

Japanese Patent Laid-Open No. 6-174848

  In general, nuclear reactors are equipped with multiple reactor shutdown systems to ensure that the fission reaction is stopped even in an emergency. However, as an accident outside the design standard, a scram failure accident or the like occurs when the flow rate is reduced in the liquid metal cooling reactor 1, and when the temperature of the liquid metal 3 rises and a considerable number of fuel cladding tubes are damaged, the nuclear fuel core 2 The gaseous component in the fission product (FP) that has been transferred to the cover gas region 4. When the FP gas accumulates in the cover gas region, since the FP gas is at high temperature and high pressure, the pressure and temperature of the cover gas region 4 increase due to the transition of the FP gas, and the liquid metal 3 and the cover gas region 4 that are coolants. If the allowable value of the boundary is exceeded, the boundary may be damaged.

  In such a case, a part of the FP gas may be transferred to the guard vessel 7 or the storage dome 8, and the FP gas may be released from the guard vessel 7 or the storage dome 8 into the reactor building.

  The conventional reactor vessel auxiliary cooling system (RVACS) described above is designed to remove the residual decay heat generated from the core against such an accident outside the design standard. In order to cool the cover gas region 4 through the wall surface, it is necessary to secure a sufficient air flow path for heat removal, which causes the problem of increasing the size of the reactor and increasing the cost. there were.

  The present invention has been made to solve the above-mentioned problems, and even in the case of an accident outside the design standard in which a considerable number of fuel damage accidents occur, the cover gas region is reliably and efficiently cooled to provide the cover gas. An object of the present invention is to provide a residual heat removal apparatus for a reactor that can ensure the soundness of the reactor coolant boundary by reducing the temperature and pressure of the region.

  In order to solve the above problems, a residual heat removal apparatus for a nuclear reactor according to the present embodiment includes a nuclear reactor vessel having a liquid metal therein, a cover gas region provided in an upper portion of the nuclear reactor vessel, A residual heat removal apparatus for a nuclear reactor having a radiation detection device for detecting radiation in a cover gas region, comprising a discharge port disposed in the cover gas region and for discharging the liquid metal to the cover gas region A discharge pipe and a suction pipe for sucking and supplying the liquid metal in the reactor vessel to the discharge pipe are provided.

  Further, the reactor residual heat removal apparatus according to the present embodiment includes a nuclear reactor vessel having a liquid metal therein, a cover gas region provided in an upper portion of the nuclear reactor vessel, and radiation in the cover gas region. In a residual heat removal apparatus for a nuclear reactor having a radiation detection apparatus for detection, a suction pipe disposed in the cover gas region for sucking a cover gas, and discharging the sucked cover gas into the liquid metal And a discharge pipe having a discharge port.

  Further, the reactor residual heat removal apparatus according to the present embodiment includes a nuclear reactor vessel having a liquid metal therein, a cover gas region provided in an upper portion of the nuclear reactor vessel, and radiation in the cover gas region. In a nuclear reactor residual heat removal apparatus having a radiation detection device for detection, a ring-shaped discharge pipe disposed around a reactor upper structural member in the liquid metal, and an inert gas in the discharge pipe A gas transfer pipe to be supplied and a plurality of discharge ports provided in the discharge pipe for discharging an inert gas upward are provided.

  Further, the reactor residual heat removal apparatus according to the present embodiment includes a nuclear reactor vessel having a liquid metal therein, a cover gas region provided in an upper portion of the nuclear reactor vessel, and radiation in the cover gas region. A residual heat removal apparatus for a nuclear reactor having a radiation detection apparatus for detecting a first discharge pipe having a discharge port disposed in the cover gas region and for discharging the liquid metal to the cover gas region; A first suction pipe for sucking the liquid metal in the reactor vessel and supplying it to the discharge pipe, a second suction pipe arranged in the cover gas region for sucking the cover gas, and the sucked cover And a second discharge pipe having a discharge port for discharging the gas into the liquid metal.

  According to the present invention, the soundness of the reactor coolant boundary is ensured by reliably and efficiently cooling the cover gas region and reducing the temperature and pressure of the cover gas region even in the event of an accident outside the design standard. can do.

(A) is sectional drawing of the liquid metal cooling nuclear reactor provided with the residual heat removal apparatus which concerns on 1st Embodiment, (b) is the sectional view on the AA line of (a). The front view of the discharge port shown in FIG. 1 which shows the structure of the porous member of the residual heat removal apparatus which concerns on 2nd Embodiment. (A) is a front view of discharge | emission piping of the residual heat removal apparatus which concerns on 3rd Embodiment, (b) is the sectional drawing. The perspective view of the discharge piping of the residual heat removal apparatus which concerns on 4th Embodiment. (A) is sectional drawing of the liquid metal cooling nuclear reactor provided with the residual heat removal apparatus which concerns on 5th Embodiment, (b) is BB sectional drawing of (a). Sectional drawing of the liquid metal cooling nuclear reactor provided with the residual heat removal apparatus which concerns on 6th Embodiment. Sectional drawing of the liquid metal cooling nuclear reactor provided with the residual heat removal apparatus which concerns on 8th Embodiment, (b) is CC sectional view taken on the line of (a). Sectional drawing of a conventional liquid metal cooled nuclear reactor.

  Hereinafter, an embodiment of a residual heat removal apparatus for a nuclear reactor according to the present invention will be described with reference to the drawings.

[First Embodiment]
A reactor residual heat removal apparatus according to a first embodiment will be described with reference to FIGS. 1 and 2.
In FIG. 1, the reactor vessel auxiliary cooling system (RVACS) is omitted.

(Constitution)
In the liquid metal cooled nuclear reactor according to the first embodiment, a radiation measuring instrument 24 for monitoring the radiation in the cover gas region 4 is installed outside the reactor vessel 5. A suction pipe 21 for sucking the liquid metal 3 in the reactor vessel 5 by the liquid metal transport device 20 and a discharge pipe 19 for releasing the liquid metal 3 sucked from the liquid metal suction pipe 21 are installed in the cover gas region 4. Has been.

  The discharge pipe 19 is provided, for example, in the upper part of the cover gas region 4, and the cross-sectional shape of the discharge port 19a of the discharge pipe 19 is a hollow shape as shown in FIG. The liquid metal transport device 20 is supplied with necessary power from a power source 23 installed outside the storage dome 8 via a power cable 22 that penetrates the shielding plug 18. A plurality of residual heat removal devices including the discharge pipe 19 and the suction pipe 21 are appropriately installed in the inner peripheral direction of the reactor vessel 5.

(Function)
In the residual heat removal apparatus configured as described above, when the FP gas moves from the nuclear fuel core 2 to the cover gas region 4, the radiation dose in the cover gas region 4 increases. By measuring the radiation dose in the cover gas region 4 by the radiation measuring instrument 24, the FP gas in the cover gas region 4 is detected. When the measured radiation dose exceeds a predetermined value, the liquid metal transport device 20 is activated. Is done.

  The liquid metal 3 sucked from the suction pipe 21 by the activation of the liquid metal transport device 20 is sprayed into the cover gas region 4 from the discharge port 19a of the discharge pipe 19 installed in the upper part of the cover gas region 4. Since the sprayed mist-like liquid metal 3 has a large contact heat transfer area, it efficiently exchanges heat with the high-temperature cover gas containing the surrounding FP gas, and the liquid metal evaporates to cause the surrounding high-temperature cover gas by latent heat of vaporization. Cool down.

  Further, the evaporated liquid metal gas is condensed at the lower part of the shielding plug 18, the side surface of the reactor vessel 5 or the liquid surface of the liquid metal 3, and is transferred again into the liquid metal 3 in the reactor vessel 5. 4 can be reduced in pressure and temperature. By continuing this, the temperature and pressure of the cover gas in the cover gas region 4 can be reduced.

(effect)
A constant cooling effect can be assumed by increasing the evaporation amount of the liquid metal 3 from the liquid surface of the liquid metal 3 when the cover gas temperature rises, but in this embodiment, the cover gas region 4 contains the reactor vessel 5 in the reactor gas 5. By spraying the liquid metal 3 directly, a substantial liquid contact area between the cover gas containing the FP gas and the liquid metal 3 is increased, and a decrease in the cover gas temperature is promoted by increasing the heat transfer area.

Further, the evaporated liquid metal 3 condenses on the lower part of the shielding plug 18, the inner peripheral surface of the reactor vessel 5 or the liquid surface of the liquid metal 3, and heat is transferred to the structural material or the liquid metal 3, so that the cover gas region is early. Pressure and temperature can be reduced.
Furthermore, since the liquid metal 3 filling the reactor vessel 3 is circulated, no facility for separately securing and supplying a cooling liquid metal is required.

  As described above, according to the first embodiment, the temperature and pressure of the cover gas region are reduced by reliably and efficiently cooling the cover gas region even in the event of an accident outside the design standard. The soundness of the reactor coolant boundary can be ensured.

[Second Embodiment]
A residual heat removal apparatus for a nuclear reactor according to a second embodiment will be described with reference to FIG.
In the second embodiment, a porous member 25 having a plurality of small-diameter holes 25 a is installed in the discharge port 19 a of the liquid metal discharge pipe 19.

  As a result, when the liquid metal 3 passing through the liquid metal discharge pipe 19 passes through the porous member 25 installed at the discharge port 19 a, it is more finely misted and discharged to the cover gas region 4.

  According to the second embodiment, since the liquid metal 3 discharged to the cover gas region 4 is discharged in a finer mist form, the liquid metal 3 is dispersed over the entire space of the cover gas region 4 over a wide range. In addition, it is possible to further improve the heat exchange efficiency by increasing the substantial liquid contact area with the high-temperature cover gas. Thereby, the temperature and pressure of a cover gas area | region can be reduced efficiently.

[Third Embodiment]
A reactor residual heat removal apparatus according to a third embodiment will be described with reference to FIGS.
In the third embodiment, a rotatable blade 27 is installed at the discharge port 19 a of the liquid metal discharge pipe 19. The blade 27 is installed in the vicinity of the discharge port 19a by the support member 28, and rotates using the fluid force of the passing liquid metal 3. The liquid metal 3 is agitated by the rotational force of the blades 27 installed at the discharge port 19 a of the discharge pipe 19 and dispersed in a mist shape over the entire cover gas region 4.

  According to the third embodiment, since the mist-like liquid metal 3 discharged to the cover gas region 4 can be discharged into the space of the cover gas region 4 in a wide range, the cooling of the cover gas region, The pressure reduction efficiency can be further improved.

[Fourth Embodiment]
A residual heat removal apparatus for a nuclear reactor according to a fourth embodiment will be described with reference to FIG.
In the fourth embodiment, the discharge pipe 26 connected to the suction pipe 21 is configured to be a curved pipe along the inner peripheral surface of the reactor vessel 5 as shown in FIG. A plurality of residual heat removal devices including the suction pipe 21 and the curved discharge pipe 26 are appropriately installed along the inner peripheral surface of the reactor vessel 5.

  The curved discharge pipe 26 is provided with a plurality of discharge ports 26 a toward the cover gas region 4. Further, the porous member 25 shown in FIG. 2 or the blade 27 shown in FIG. 3 may be installed at the discharge port 26a, whereby the mist-like liquid metal 3 is discharged toward the cover gas region 4 from each discharge port 26a. Is done.

  According to the third embodiment, by arranging the curved discharge pipe along the inner peripheral surface of the reactor vessel, the liquid metal 3 discharged to the cover gas region 4 is It is possible to spray the entire space more uniformly over a wide range in a short time, and the substantial liquid contact area with the cover gas can be increased, further improving the cooling and decompression efficiency of the cover gas region. Can be made.

[Fifth Embodiment]
A nuclear reactor residual heat removal apparatus according to a fifth embodiment will be described with reference to FIGS.
In the fifth embodiment, the ring-shaped discharge pipe 29 is installed around the upper structural member 9 in the furnace in the cover gas region 4, and the liquid metal transport device 20 and the liquid metal suction pipe 21 are connected to the upper structural member in the furnace. Install along line 9. In the ring-shaped discharge pipe 29, a plurality of discharge ports 29a for discharging the liquid metal are provided in a circumferential shape. Further, the porous member 25 shown in FIG. 2 or the blade 27 shown in FIG. 3 may be installed at the discharge port 29a.

  The liquid metal 3 sucked by the liquid metal suction pipe 21 is sprayed uniformly in a mist form into the cover gas region 4 from the discharge port 29a of the ring-shaped discharge pipe 29.

According to the fifth embodiment, the ring-shaped discharge pipe 29 is installed around the upper structure 9 in the reactor, so that the mist from the central position of the reactor vessel 5 toward the inner peripheral surface of the reactor vessel 5 is increased. The liquid metal 3 can be sprayed uniformly over the entire cover gas region 4 in a short time, and the substantial liquid contact area with the cover gas can be further increased. The pressure can be reduced efficiently in a short time.
Further, when the first to fourth embodiments are used in combination, the liquid metal 3 is released from both the central portion and the outside of the cover gas region 4 and can be dispersed more uniformly.

[Sixth Embodiment]
A reactor residual heat removal apparatus according to a sixth embodiment will be described with reference to FIG.
(Constitution)
In the present embodiment, the cover gas suction pipe 32 is provided in the cover gas region 4, the cover gas in the cover gas region 4 is sucked by the suction blower 31 provided in the discharge pipe 33, and the cover gas is discharged from the discharge pipe 33 into the liquid metal 3. It is set as the structure discharge | released.

  The discharge port 33a of the discharge pipe 33 is configured in the opening shape shown in FIG. 1A, or the porous member 25 shown in FIG. 2 is installed. The suction blower 31 is operated by a blower drive motor 29 installed outside the reactor vessel 5. A plurality of residual heat removal devices including the cover gas suction pipe 32 and the discharge pipe 33 are appropriately installed in the inner peripheral surface direction of the reactor vessel 5.

(Function)
In the residual heat removal apparatus configured as described above, the suction blower 31 is activated when the radiation dose detected by the radiation measuring instrument 24 exceeds a predetermined value. When the suction blower 31 is activated, the cover gas in the cover gas region 4 is sucked from the suction pipe 32 and discharged from the discharge port 33 a of the discharge pipe 33 into the liquid metal 3. By continuing this, the temperature of the cover gas region 4 decreases.

(effect)
When the cover gas containing the FP gas whose temperature has been raised by the heat generation of the FP gas is released into the liquid metal 3, the temperature is lowered by coming into contact with the low temperature liquid metal 3 and is released again into the cover gas region 4. . Thereby, the temperature of the cover gas area | region 4 falls. Further, by using the porous member 25 for the discharge port 33a, the substantial heat transfer area between the cover gas and the liquid metal 3 can be increased, and the cooling efficiency of the cover gas can be improved.

Furthermore, since the cover gas sucked from the cover gas suction pipe 32 circulates through the liquid metal 3 filling the reactor vessel 5 and the cover gas region 4, it is not necessary to prepare a separate cooling device.
According to the sixth embodiment, it is possible to improve the cooling and decompression efficiency of the cover gas region by releasing and circulating the cover gas in the cover gas region into the liquid metal.

[Seventh Embodiment]
A reactor residual heat removal apparatus according to a seventh embodiment will be described.
The residual heat removal apparatus of the seventh embodiment is characterized in that the residual heat removal apparatus of the first to fifth embodiments and the residual heat removal apparatus of the sixth embodiment are used in combination.

  For example, the residual heat removal apparatus including the suction pipe 21 and the discharge pipe 19 according to the first embodiment (FIG. 1), and the residual heat removal apparatus including the suction pipe 32 and the discharge pipe 33 according to the sixth embodiment (FIG. 7). Use together. At that time, it is desirable that the discharge pipe 19 is set lower than the suction pipe 32.

Thereby, the discharge of the mist-like liquid metal 3 to the cover gas region 4 by the electromagnetic pump 20 and the discharge of the cover gas including the FP gas into the liquid metal 3 by the suction blower 31 are simultaneously performed without interfering with each other. Since it becomes possible to implement, the temperature and pressure of a cover gas area | region can be reduced reliably and efficiently.
Further, even if the residual heat removal apparatus according to the second to fifth embodiments and the residual heat removal apparatus according to the sixth embodiment are used in combination, the same effect can be obtained.

  According to the seventh embodiment, it is possible to improve the reliability and cooling efficiency of the residual heat removal device by reducing the pressure and cooling the cover gas region by two different methods, and the discharge pipe 19 By installing it lower than the suction pipe 32, it is possible to prevent the liquid metal 3 discharged from the discharge pipe 19 from being mixed into the suction pipe 32. As a result, it is possible to avoid deterioration of the function of the blower and maintain the cooling and decompression functions of the cover gas region for a long period of time.

[Eighth Embodiment]
A reactor residual heat removal apparatus according to an eighth embodiment will be described with reference to FIG.
(Constitution)
In the residual heat removal apparatus according to the present embodiment, a ring-shaped discharge pipe 38 is installed around the upper structural member 9 in the furnace in the liquid metal 3 and is filled with an inert gas installed outside the storage dome 8. The inert gas is supplied from the gas tank 35 to the ring-shaped discharge pipe 38 via the gas transfer pipe 37. The ring-shaped discharge pipe 38 is provided with a plurality of discharge ports 38 a on the cover gas region 4 side, that is, on the upper part of the ring-shaped discharge pipe 38. In addition, you may install the porous member 25 shown in FIG. 2 in the discharge port 38a.

  In addition, a valve 36 is installed in the gas transfer pipe 37, and a high-pressure inert gas in the gas tank 35 is supplied to the ring-shaped gas discharge pipe 38 by opening and closing the valve 36 without using a dynamic device. .

(Function)
When the radiation dose in the cover gas region 4 measured by the radiation measuring instrument 24 exceeds a predetermined value, the valve 36 is opened. The inert gas filled in the high-pressure gas tank 35 is transferred to the discharge pipe 38 using the filling pressure, and is discharged upward below the water surface of the liquid metal 3.

  The liquid surface of the liquid metal 3 is agitated by the inert gas released toward the cover gas region 4, and a part of the liquid metal 3 is dispersed in the cover gas region 4 in the form of a mist. The sprayed mist-like liquid metal 3 cools the hot cover gas, partially evaporates and condenses on the upper part of the shielding plug, the side surface of the reactor vessel 5 or the surface of the liquid metal 3, and again in the liquid metal 3. Transition. By continuing this according to the capacity of the inert gas accumulated in the gas tank 35, the temperature and pressure of the cover gas region 4 are lowered.

(effect)
By releasing the inert gas upward below the liquid metal 3, the liquid surface of the liquid metal 3 is agitated to be mist, and the cover gas in the cover gas region 4 and the mist of the liquid metal 3 are substantially separated. By increasing the typical liquid contact area, the temperature and pressure of the cover gas can be efficiently reduced.

  Further, since the liquid metal 3 in the reactor vessel 5 is used, there is no need to separately prepare a cooling liquid metal and incidental equipment. Furthermore, since the inert gas is transported using the pressure of the high-pressure gas tank 35, a dynamic device for transporting the inert gas is not required.

  According to the eighth embodiment, the inert gas is discharged from the ring-shaped discharge pipe into the liquid metal without using a dynamic device, thereby ensuring the pressure and temperature of the cover gas in the cover gas region. And can be reduced efficiently.

The residual heat removal apparatus according to the eighth embodiment can also be used in combination with the residual heat removal apparatus according to the other embodiments.
Further, although the embodiment of the present invention has been described by taking a liquid metal cooled nuclear reactor as an example, it is needless to say that the present invention is not limited to a liquid metal cooled nuclear reactor and can be applied to a nuclear reactor having a cover gas region.

  As mentioned above, although the example of the embodiment of the present invention has been described, only a specific example has been illustrated, and the present invention is not particularly limited, and a specific target liquid metal cooling furnace or the like can be changed as appropriate. is there. Further, the actions and effects described in the embodiments and the modifications thereof are only the most preferable actions and effects resulting from the present invention, and the actions and effects according to the present invention are described in the embodiments of the present invention. It is not limited to the ones.

  DESCRIPTION OF SYMBOLS 1 ... Liquid metal cooling reactor, 2 ... Nuclear fuel core, 3 ... Liquid metal, 4 ... Cover gas area, 5 ... Reactor vessel, 7 ... Guard vessel, 8 ... Containment dome, 9 ... Upper structural member in a reactor, 10 ... Collector, 11 ... Air descending channel, 12 ... Air rising channel, 13 ... Annular space, 14 ... Air inlet, 15 ... Steel liner, 16 ... Concrete structure, 17 ... Duct, 18 ... Shielding plug, 19 ... Discharge pipe, 19a ... discharge port, 20 ... liquid metal transport equipment, 21 ... suction pipe, 24 ... radiation measuring instrument, 25 ... porous member, 26 ... discharge pipe, 26a ... discharge port, 27 ... vane, 29 ... discharge pipe, 29a ... discharge port, 31 ... suction blower, 32 ... suction pipe, 33 ... discharge pipe, 33a ... discharge port, 37 ... gas transfer pipe, 38 ... discharge pipe, 38a ... discharge port.

Claims (9)

Residual heat removal of a nuclear reactor having a nuclear reactor vessel holding a liquid metal therein, a cover gas region provided on the upper portion of the nuclear reactor vessel, and a radiation detection device for detecting radiation in the cover gas region In the device
A discharge pipe that is disposed in the cover gas region and has a discharge port for discharging the liquid metal to the cover gas region; and a suction pipe that sucks the liquid metal in the reactor vessel and supplies the liquid metal to the discharge pipe. An apparatus for removing residual heat from a nuclear reactor.   2. The residual heat removal apparatus for a reactor according to claim 1, wherein the discharge pipe is curved along the inner surface of the reactor vessel, and a plurality of discharge ports are provided in the discharge pipe.   2. The liquid metal cooling according to claim 1, wherein the discharge pipe is ring-shaped, and the discharge pipe is arranged around the upper structural member in the furnace in the cover gas region and provided with a plurality of discharge ports. Reactor residual heat removal equipment. Residual heat removal of a nuclear reactor having a nuclear reactor vessel holding a liquid metal therein, a cover gas region provided on the upper portion of the nuclear reactor vessel, and a radiation detection device for detecting radiation in the cover gas region In the device
A suction pipe disposed in the cover gas region for sucking the cover gas and a discharge pipe provided with a discharge port for discharging the sucked cover gas into the liquid metal. Reactor residual heat removal equipment. Residual heat removal of a nuclear reactor having a nuclear reactor vessel holding a liquid metal therein, a cover gas region provided on the upper portion of the nuclear reactor vessel, and a radiation detection device for detecting radiation in the cover gas region In the device
A ring-shaped discharge pipe arranged around the upper structural member in the furnace in the liquid metal, a gas transfer pipe for supplying an inert gas to the discharge pipe, and the inert gas provided in the discharge pipe upward An apparatus for removing residual heat from a nuclear reactor comprising a plurality of discharge ports for discharging. Residual heat removal of a nuclear reactor having a nuclear reactor vessel holding a liquid metal therein, a cover gas region provided on the upper portion of the nuclear reactor vessel, and a radiation detection device for detecting radiation in the cover gas region In the device
A first discharge pipe disposed in the cover gas region and provided with a discharge port for discharging the liquid metal into the cover gas region; and a first discharge pipe for sucking the liquid metal in a reactor vessel and supplying the liquid metal to the discharge pipe A second suction pipe disposed in the cover gas region for sucking the cover gas, and a discharge port for discharging the sucked cover gas into the liquid metal. An apparatus for removing residual heat from a nuclear reactor comprising a discharge pipe.   The residual heat removal apparatus for a nuclear reactor according to claim 6, wherein the first discharge pipe and the second suction pipe are installed at different heights.   A porous member is provided at the discharge port for discharging the liquid metal into the cover gas region, the discharge port for discharging the inert gas upward, or the discharge port for discharging the sucked cover gas into the liquid metal. The apparatus for removing residual heat of a nuclear reactor according to any one of claims 1 to 7, wherein   The apparatus for removing residual heat from a nuclear reactor according to any one of claims 1 to 3, wherein a rotary vane is installed at a discharge port for discharging the liquid metal into a cover gas region.

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