JP2016223814A - Heat removal device and nuclear reactor facility - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a heat removal device capable of supplying a coolant into a reactor pressure vessel without using electric power, and a nuclear reactor facility.SOLUTION: A heat removal device 15A is used for a nuclear reactor facility 10A that has a reactor containment vessel 12 containing a reactor pressure vessel 11 and a pressure-suppression chamber 14 storing pool water W1 that condenses vapor released into the reactor containment vessel 12. The heat removal device 15A comprises: a vapor-supply tube 32A; a vapor injector 31A; and a water-supply tube 33. The vapor-supply tube 32A allows supply of the vapor in the reactor containment vessel 12. The vapor injector 31A has a nozzle, a throat, and a diffuser to which the pool water W1 is supplied. The vapor from the vapor-supply tube 32A is supplied to the throat through the nozzle. The pool water W1 is discharged toward the downstream side of the diffuser. The water-supply tube 33 connects the vapor injector 31A and the reactor pressure vessel 11.SELECTED DRAWING: Figure 1

Description

  Embodiments described herein relate generally to a heat removal apparatus and nuclear reactor equipment.

  In a nuclear power plant equipped with nuclear reactor equipment, when coolant piping connected to the reactor pressure vessel breaks, high-temperature and high-pressure reactor primary coolant (hereinafter referred to as “coolant”) is contained in the reactor containment vessel. A reactor coolant loss accident (hereinafter referred to as “LOCA”) may occur.

  For example, when LOCA occurs in a boiling water nuclear power plant, when high-temperature and high-pressure coolant is released to the dry well in the reactor containment vessel, the temperature and pressure in the dry well rapidly increase. In order to prevent radioactive material from being released outside the containment during LOCA, the nuclear power plant is responsible for the high temperature and high pressure released into the drywell before reaching the design and design pressure of the containment. The coolant is discharged into the pressure suppression chamber through the vent pipe and absorbed into the suppression pool water (hereinafter referred to as “pool water”) in the suppression pool (hereinafter referred to as “pool water”). The temperature and pressure in the furnace containment vessel are reduced.

  Also, when LOCA occurs, if the coolant is lost without returning to the reactor pressure vessel due to the breakage of the coolant piping, the water level in the reactor pressure vessel is lowered, the core is exposed, and the decay heat generated in the core Severe accidents (SA) can occur where cooling is inadequate and core melting is possible. Therefore, nuclear power plants are equipped with an emergency core cooling system, a containment vessel cooling system, and an auxiliary cooling system that transfers these heats to the final heat sink to ensure complete safety. In addition, the decay heat generated in the core can be removed over a long period of time. As an emergency core cooling system, for example, an emergency core cooling device (hereinafter referred to as “ECCS”) using pool water as a water source is provided. When the ECCS is operated, the reactor pressure vessel is cooled. Water is injected and the core is submerged to prevent core melting.

  Should the reactor pressure vessel break down as the reactor pressure vessel temperature rises, the core melt will fall to the bottom of the drywell and come out of the reactor pressure vessel and come into direct contact with the pool water. A large amount of water vapor is then generated. As the concentration of hydrogen gas generated from the water vapor increases, the pressure inside the reactor containment vessel or the water vapor explosion may occur. In such a case, a heat removal device is used to remove heat in the reactor containment vessel, thereby reducing the hydrogen partial pressure or condensing the steam, thereby increasing the pressure in the reactor containment vessel and the steam. It prevents explosions and ensures the safety of the reactor.

  In the conventional heat removal apparatus, for example, when the water in the water storage tank is supplied to a jet pump submerged in the pool water of the pressure suppression chamber, the water in the pressure suppression chamber is replaced by an alternative water injection pump by the jet pump. It is sucked into the suction side. And the water supplied to the suction side of the alternative water injection pump is cooled and then supplied into the reactor pressure vessel and used to cool the reactor core and the containment vessel. It is said.

JP2012-230059A

  However, in the conventional heat removal apparatus, the power for operating the water injection pump is necessary, or the countermeasure when the power is lost has not been sufficiently considered. In the future, in order to ensure further safety of the reactor, there is a demand for a heat removal device that can cool the reactor effectively by supplying coolant into the reactor without power.

  Therefore, the problem to be solved by the present invention is to provide a heat removal apparatus and a reactor facility that can supply pool water into a reactor pressure vessel without using electric power.

  A heat removal apparatus according to an embodiment includes a nuclear reactor containment vessel that contains a reactor pressure vessel, and a pressure suppression chamber that contains pool water that condenses steam released into the reactor containment vessel. A heat removal apparatus for use in nuclear reactor equipment, a steam supply pipe configured to be able to supply the steam inside the reactor containment vessel, a nozzle unit, a throat unit, and a diffuser unit to which the pool water is supplied A steam injector configured to supply the steam from the steam supply pipe to the throat section at the nozzle section, and to discharge the pool water to the downstream side of the diffuser section, and the steam injector; And a water supply pipe connecting the reactor pressure vessel.

  A reactor installation according to another embodiment includes a reactor containment vessel that contains a reactor pressure vessel, a pressure suppression chamber that contains pool water for condensing steam supplied from the reactor containment vessel, and the above-described removal. And a heat device.

  According to the present invention, pool water can be supplied into a reactor pressure vessel without using electric power.

It is a figure which shows the structure of the nuclear reactor equipment to which the heat removal apparatus by 1st Embodiment is applied. It is a figure which shows the structure of a steam injector. It is a figure which shows the structure of the nuclear reactor installation to which the heat removal apparatus by 2nd Embodiment is applied. It is a figure which shows the structure of a steam injector. It is a figure which shows the structure of the nuclear reactor equipment to which the heat removal apparatus by 3rd Embodiment is applied. It is a figure which shows the structure of the nuclear reactor equipment to which the heat removal apparatus by 4th Embodiment is applied. It is explanatory drawing which shows the mixing state of the steam and water in an auxiliary steam injector. It is a figure which shows the structure of the nuclear reactor equipment to which the heat removal apparatus by 5th Embodiment is applied.

  Hereinafter, embodiments of the present invention will be described in detail.

(First embodiment)
The nuclear reactor equipment to which the heat removal apparatus according to the first embodiment is applied will be described with reference to the drawings. In the following description, one of the reactor facilities in the height direction may be referred to as “upper” or “upper”, and the other of the reactor facilities in the height direction may be referred to as “lower” or “lower”.

  FIG. 1 is a diagram illustrating a configuration of a nuclear reactor facility to which a heat removal apparatus according to the first embodiment is applied. As shown in FIG. 1, a reactor facility 10 </ b> A includes a reactor pressure vessel 11, a reactor containment vessel 12, a vent pipe 13, a pressure suppression chamber 14, a heat removal device 15 </ b> A, and a heat exchanger (heat exchange unit) 16. Have.

  The reactor pressure vessel 11 contains a core 21 and is accommodated in a dry well 22 in the reactor containment vessel 12. A main steam pipe 23 is connected to the reactor pressure vessel 11. The main steam pipe 23 is connected to a steam turbine (not shown) disposed outside the reactor pressure vessel 11. The steam generated inside the reactor pressure vessel 11 is supplied to a steam turbine (not shown) through the main steam pipe 23.

  A main steam relief safety valve 24 is provided in the middle of the main steam pipe 23 in the reactor containment vessel 12. A relief safety valve discharge pipe 25 is connected to the downstream side of the main steam relief safety valve 24, and a discharge port of the relief safety valve discharge pipe 25 is provided in the pressure suppression chamber 14. The relief safety valve discharge pipe 25 is communicated with the pressure suppression chamber 14 from the main steam relief safety valve 24 through the vent pipe 13.

  The reactor containment vessel 12 is installed in the reactor building, and the reactor pressure vessel 11 is accommodated in an internal dry well 22.

  A plurality of vent pipes 13 are connected at predetermined intervals in the circumferential direction below the reactor containment vessel 12, and connect the reactor containment vessel 12 and the pressure suppression chamber 14. The reactor containment vessel 12 and the pressure suppression chamber 14 are communicated with each other through a vent pipe 13, and the steam released into the reactor containment vessel 12 is supplied into the pressure suppression chamber 14 through the vent pipe 13.

  The pressure suppression chamber 14 is formed in an annular shape so as to concentrically surround the lower outer periphery of the reactor containment vessel 12. The pressure suppression chamber 14 contains pool water W1 therein, and condenses steam supplied from the reactor containment vessel 12 through the vent pipe 13. In the present embodiment, the steam released into the dry well 22 of the reactor containment vessel 12 by the opening of the main steam relief safety valve 24 is supplied into the pool water W1 in the pressure suppression chamber 14 by the vent pipe 13. Cool and condense. In the present embodiment, the steam released into the dry well 22 is not limited to steam, but a mixture of steam and water, a mixture of steam and other additives, or steam, water and additives. Etc., and a mixture thereof.

  The heat removal device 15A is for cooling the reactor pressure vessel 11 by supplying pool water W1 to the reactor pressure vessel 11, and includes a steam injector 31A, a steam supply pipe 32A, a water supply pipe 33, And a discharge valve 34.

  The steam injector 31 </ b> A is provided in a state of being submerged in the pool water W <b> 1 in the pressure suppression chamber 14. In the steam injector 31A, the tip of the steam supply pipe 32A is partially inserted into the water supply port 31a, and the water supply pipe 33 is connected to the discharge port 31b that discharges the pool water W1.

  As shown in FIG. 2, the steam injector 31 </ b> A includes a nozzle portion 35, a throat portion 38, and a diffuser portion 39, which are arranged in series in order from the upstream side to configure the flow path.

  The nozzle part 35 includes an introduction part 36 and a mixing part 37. Each of the introduction part 36 and the mixing part 37 has a shape in which the internal cross-sectional area decreases in the traveling direction of the steam flow. In this embodiment, the introduction part 36 and the mixing part 37 are both circular in cross section, but may be other shapes such as a rectangle.

  The introduction part 36 has a nozzle-like steam introduction part 36a and a water introduction part 36b. The steam introduction part 36a introduces the steam supplied from the steam supply pipe 32B. The water introduction part 36b is formed on the outer periphery of the steam introduction part 36a and introduces the pool water W1 in the pressure suppression chamber 14. The steam is jetted by the nozzle-shaped steam introduction part 36a and introduced into the steam injector 31A. Moreover, the pool water W1 introduced from the water introduction part 36b is merged with the jet-like steam introduced from the steam introduction part 36a from the outer peripheral side of the steam.

  In the mixing unit 37, the pool water W1 and the steam are mixed to form a fluid in a gas-liquid mixed state. The steam is rapidly cooled and condensed by the pool water W1, and its volume is greatly reduced. Therefore, a space is generated in the steam injector 31A due to the condensation of the steam, and a negative pressure is generated inside the mixing unit 37. As a result, the pool water W1 is sucked into the space generated along with the condensation of the steam from the water supply port 31a of the steam injector 31A, and enters the steam injector 31A through the water introduction part 36b. Further, due to the negative pressure generated inside the mixing unit 37, the flow rate of the steam introduced into the steam injector 31A increases, and the flow rate of the pool water W1 sucked from the water supply port 31a also increases.

  The throat portion 38 is formed on the outlet side of the mixing portion 37 and on the inlet side of the diffuser portion 39. In the present embodiment, the throat portion 38 has a circular cross section, but may have another shape such as a rectangular cross section. The throat portion 38 is a portion extending from the mixing portion 37 to the diffuser portion 39 and having the smallest internal cross-sectional area. Therefore, the pool water W1 has the highest flow velocity when passing through the throat portion 38.

  The diffuser portion 39 has a shape in which the internal cross-sectional area increases from the throat portion 38 toward the traveling direction of the pool water W1. In the present embodiment, the diffuser portion 39 has a circular cross section, but may have another shape such as a rectangular cross section. Since the internal cross-sectional area of the diffuser part 39 is expanding, the pool water W1 has a low flow velocity and a high pressure. As a result, in the diffuser unit 39, the pressure of the pool water W1 is increased and discharged from the discharge port 31b as the pool water W2.

  That is, in the present embodiment, the steam injector 31A supplies the steam from the steam supply pipe 32B toward the throat portion 38 at the nozzle portion 35, and supplies the pool water W1 from the nozzle portion 35 to the downstream side of the diffuser portion 39. It is comprised so that it can discharge.

  The steam supply pipe 32A is provided between the vent pipe 13 communicating with the reactor containment vessel 12 and the steam injector 31A, and connects the dry well 22 of the reactor containment vessel 12 and the steam injector 31A. When LOCA or the like occurs, the steam supply pipe 32A is configured to be able to supply water vapor generated inside the reactor pressure vessel 11 to the steam injector 31A via the inside of the reactor containment vessel 12. The steam introduction part 36a of the steam supply pipe 32B is disposed so as to be located in the introduction part 36 where the radial direction with respect to the axial direction of the steam injector 31A is narrowed.

  The water supply pipe 33 connects the steam injector 31A and the reactor pressure vessel 11, and communicates with the discharge port 31b of the diffuser portion 39 of the steam injector 31A. The discharged pool water W2 is discharged from the steam injector 31A to the water supply pipe 33.

  The water supply pipe 33 may be connected to the reactor containment vessel 12 in addition to being connected to the reactor pressure vessel 11 so as to supply water into the reactor containment vessel 12. Further, the water supply pipe 33 is connected to the reactor pressure vessel 11, but a part of the downstream side of the water supply pipe 33 is a reactor such as a water supply system, a high pressure core spray system, a core spray system, and a low pressure water injection system. You may connect to the existing coolant supply pipe of other systems, such as piping connected to.

  The discharge valve 34 is provided in the discharge port 31b of the steam injector 31A. The discharge valve 34 normally closes the discharge port 31b of the steam injector 31A, but the discharge force of the steam supplied into the steam injector 31A becomes large and is discharged from the discharge port 31b in the event of a nuclear reactor accident or the like. When the pressure of the pool water W2 rises, the discharge valve 34 opens and the pool water W2 is supplied from the steam injector 31A to the water supply pipe 33. In the present embodiment, the discharge valve 34 is provided, but it may not be provided.

  The heat exchanger 16 is provided in the middle of the water supply pipe 33, and cools the pool water W <b> 2 flowing through the water supply pipe 33. The heat exchanger 16 only needs to be able to cool the pool water W2, and for example, an air fin cooler or the like is used. The air fin cooler, for example, blows air to a heat exchanger that passes the pool water W2, a plurality of air cooling fins disposed on the outer surface of the heat exchanger, and the heat exchanger and the air cooling fins. And a blower.

  Next, the operation of the heat removal device 15A will be described. First, when an accident or the like has not occurred in the reactor facility 10 and normal operation is being performed, the steam generated inside the reactor pressure vessel 11 passes through the main steam pipe 23 and is illustrated. Not supplied to the steam turbine.

  On the other hand, when a nuclear accident such as LOCA occurs in the reactor facility 10 and the pressure of the reactor pressure vessel 11 rises due to the decay heat of the core 21, the steam in the reactor pressure vessel 11 is released as a main steam relief valve. 24 is opened and discharged into the reactor containment vessel 12 to depressurize the reactor pressure vessel 11. Then, the steam released into the reactor containment vessel 12 is introduced into the pool water W1 in the pressure suppression chamber 14 through the vent pipe 13, cooled, and condensed.

  Further, as shown in FIG. 2, the steam supplied from the vent pipe 13 to the steam supply pipe 32A is ejected from the steam introduction portion 36a of the steam supply pipe 32A and flows into the steam injector 31A. The steam ejected from the steam introduction part 36a is mixed with the pool water W1 flowing from the water introduction part 36b formed on the outer periphery of the steam introduction part 36a. At this time, the steam is rapidly cooled and condensed by the pool water W1, and its volume is greatly reduced. Therefore, a space is generated in the steam injector 31 </ b> A as the steam is condensed, and a negative pressure is generated in the mixing unit 37. The pool water W1 is sucked into the space generated by the condensation of the steam from the water supply port 31a of the steam injector 31A and enters the steam injector 31A from the water introduction part 36b. Further, the negative pressure generated in the mixing unit 37 increases the flow rate of the steam introduced into the steam injector 31A, and increases the flow rate of the pool water W1 sucked from the water supply port 31a. The pool water W1 has the highest flow velocity when passing through the throat portion 38. In the diffuser unit 39, the pool water W1 is decelerated and pressure-up and discharged from the discharge port 31b as pool water W2. At this time, the pool water W2 has a pressure P2 that is several times the pressure P1 of the steam flowing in from the steam nozzle 31, and is discharged from the discharge port 31b.

  Since the discharge pressure of the pool water W2 is low when the steam flows into the steam injector 31A, the discharge valve 34 closes the outlet side of the steam injector 31A, and the pool water W2 flows into the pool water W1 of the steam injector 31A. Outflow from the direction.

  When the discharge pressure of the pool water W2 increases, the discharge valve 34 opens and the pool water W2 starts to flow from the discharge port 31b to the water supply pipe 33. Since the pressure of the steam supplied to the steam supply pipe 32A is high, when the steam is supplied to the steam supply pipe 32A, the discharge pressure of the pool water W2 discharged from the steam injector 31A is the pressure of the reactor pressure vessel 11. Therefore, it can be used as a drive source when the pool water W2 is poured into the reactor pressure vessel 11 for cooling.

  Moreover, since the pool water W1 supplied to the steam injector 31A is heated by condensation of the steam, the pool water W2 discharged from the steam injector 31A to the water supply pipe 33 is cooled by the heat exchanger 16. The reactor pressure vessel 11 is supplied and used as reactor water for cooling the reactor pressure vessel 11.

  Thereby, the reactor water whose water level in the reactor pressure vessel 11 has been raised becomes steam in the reactor pressure vessel 11 and is supplied from the main steam relief safety valve 24 into the reactor containment vessel 12. The steam supplied into the reactor containment vessel 12 is returned again to the pressure suppression chamber 14, discharged from the heat removal device 15 </ b> A, and circulated to the reactor pressure vessel 11. Thereby, a closed system loop of pool water used for cooling the reactor pressure vessel 11 is formed.

  Thus, according to the present embodiment, the heat removal device 15A has the above-described configuration, and is generated in the steam injector 31A by condensation of the steam supplied from the steam supply pipe 32A to the steam injector 31A. The pool water W2 can be supplied to the water supply pipe 33 by using the suction force that sucks the pool water W1 in the pressure suppression chamber 14 into the space as a drive source. For this reason, the heat removal apparatus 15A can supply the pool water W2 to the reactor pressure vessel 11 without using electric power. Thereby, the inside of the nuclear reactor containment vessel 12 can be cooled, and the nuclear reactor can be cold stopped.

(Second Embodiment)
A heat removal apparatus according to a second embodiment will be described with reference to the drawings. In addition, the same code | symbol is attached | subjected to the member which has the same function as the said embodiment, and detailed description is abbreviate | omitted. FIG. 3 is a diagram illustrating a configuration of a nuclear reactor facility to which the heat removal apparatus according to the second embodiment is applied. As shown in FIG. 3, the nuclear reactor facility 10 </ b> B is provided with the steam injector 31 </ b> A of the heat removal apparatus 15 </ b> A of the first embodiment shown in FIG. 1 outside the pressure suppression chamber 14, and the vent pipe 13, the steam injector 31 </ b> B, Are provided with a steam supply pipe 32B for connecting the two, and a water conduit 41 for connecting the vent pipe 13 and the steam injector 31A. That is, the heat removal apparatus 15B according to the present embodiment includes a steam injector 31B, a steam supply pipe 32B, a water guide pipe 41, a water supply pipe 33, and a discharge valve 34.

  The steam injector 31B is disposed outside the pressure suppression chamber 14.

  The steam supply pipe 32B is provided between the vent pipe 13 communicating with the reactor containment vessel 12 and the steam injector 31B, and connects the dry well 22 of the reactor containment vessel 12 and the steam injector 31B. When LOCA or the like is generated, the steam supply pipe 32B is configured to be able to supply water vapor generated inside the reactor pressure vessel 11 to the steam injector 31B via the inside of the reactor containment vessel 12.

  The water conduit 41 is connected to the bottom of the pressure suppression chamber 14 and supplies the pool water W1 in the pressure suppression chamber 14 to the steam injector 31B. The water conduit 41 is connected to the bottom of the pressure suppression chamber 14. The water conduit 41 is not limited to the bottom of the pressure suppression chamber 14, but may be connected to the pressure suppression chamber 14 below the pool water surface and provided at a place lower than the pool water.

  FIG. 4 is a diagram showing the configuration of the steam injector 31B of the present embodiment. As shown in FIG. 4, the steam injector 31 </ b> B includes a nozzle portion 35, a throat portion 38, and a diffuser portion 39, similar to the steam injector 31 </ b> A shown in FIG. 2. The introduction part 36 constituting the nozzle part 35 has a nozzle-like steam introduction part 36a and a water introduction part 36b, similarly to the steam injector 31A shown in FIG. A water conduit 41 is connected to the upstream side of the water introduction part 36b, and the pool water W1 is supplied from the water conduit 41 into the water introduction part 36b.

  In this embodiment, when a nuclear accident such as LOCA occurs in the reactor facility 10B, the steam released into the reactor containment vessel 12 is supplied from the vent pipe 13 to the steam supply pipe 32B as shown in FIG. To be supplied. The steam supplied to the steam supply pipe 32B is ejected from the steam introduction part 36a of the steam supply pipe 32B and flows into the steam injector 31B. Further, when steam is supplied from the steam supply pipe 32B to the steam injector 31B, the pool water W1 in the pressure suppression chamber 14 is supplied from the water introduction part 41a of the water guide pipe 41 to the steam injector 31B. The steam ejected from the steam introduction part 36a of the steam supply pipe 32B is mixed with the pool water W1 supplied from the water introduction part 36b at the tip of the water conduit 41 as shown in FIG. At this time, the steam is rapidly cooled and condensed by the pool water W1, and its volume is greatly reduced. Therefore, a space is generated in the steam injector 31 </ b> B as the steam is condensed, and a negative pressure is generated inside the mixing unit 37. The pool water W1 supplied from the water conduit 41 is sucked into the space generated by the condensation of the steam and enters the steam injector 31B. In addition, the flow rate of the steam introduced into the steam injector 31A is increased by the negative pressure generated in the mixing unit 37, and the flow rate of the pool water W1 supplied from the water conduit 41 is increased. The pool water W1 has the highest flow velocity when passing through the throat portion 38. In the diffuser unit 39, the pool water W1 is decelerated and boosted, discharged from the discharge port 31b as pool water W2, and supplied to the water supply pipe 33.

  By supplying the steam to the steam supply pipe 32B, the discharge pressure of the pool water W2 discharged from the steam injector 31B is sufficiently higher than the pressure of the reactor pressure vessel 11, so It can be used as a drive source when the pool water W2 is poured for cooling.

  Therefore, according to the present embodiment, even if the steam injector 31B is disposed outside the pressure suppression chamber 14, the pressure suppression is performed in the space generated in the steam injector 31B due to the condensation of the steam supplied in the steam injector 31B. The pool water W2 can be supplied to the water supply pipe 33 by using the suction force that the pool water W1 in the chamber 14 is sucked in as a drive source. For this reason, the heat removal apparatus 15B can supply the pool water W2 to the reactor pressure vessel 11 without using electric power.

  Therefore, in the present embodiment, even in a situation where the steam injector 31B cannot be submerged in the pool water W1 of the pressure suppression chamber 14, the pool water W2 of the pressure suppression chamber 14 is stored in the reactor pressure vessel 11 without using power. Can be supplied as Moreover, in this embodiment, since the steam injector 31B is disposed outside the pressure suppression chamber 14 to supply the steam and the pool water W1, the degree of freedom in arranging the piping such as the steam supply pipe 32B and the water conduit 41 is provided. Can be increased.

  In addition, in 1st Embodiment shown in FIG. 1, the example in which the whole steam injector 31A is arrange | positioned in the pressure suppression chamber 14 is shown, and in this embodiment, the steam injector 31B is arrange | positioned on the outer side of the pressure suppression chamber 14. FIG. In addition to this, for example, only the introduction part 36 that is a part of the nozzle part 35 of the steam injector is provided in the pressure suppression chamber 14, and the other part is disposed outside the pressure suppression chamber 14. May be.

(Third embodiment)
A heat removal apparatus according to a third embodiment will be described with reference to the drawings. In addition, the same code | symbol is attached | subjected to the member which has the same function as the said embodiment, and detailed description is abbreviate | omitted. FIG. 5 is a diagram illustrating a configuration of a nuclear reactor facility to which the heat removal apparatus according to the third embodiment is applied. As shown in FIG. 5, the nuclear reactor facility 10 </ b> C includes steam injectors 31 </ b> A- 1 and 31 </ b> A- 2 of the heat removal apparatus 15 </ b> A of the first embodiment shown in FIG. 1, branches off from the steam supply pipe 32 </ b> A, and steam injectors A branch steam supply pipe 43 partially inserted into the supply port of 31A-2 and a water mixing pipe 44 connecting the discharge port of the steam injector 31A-2 and the water supply pipe 33 are provided. The number of steam injectors 31A is not limited to two, and three or more steam injectors may be provided, and the number of branch steam supply pipes 43 may be two or more according to the number of steam injectors 31A.

  A part of the steam flowing through the steam supply pipe 32 </ b> A is separated into the branch steam supply pipe 43. The steam separated from the branch steam supply pipe 43 passes through the branch steam supply pipe 43 and is supplied to the steam injector 31A-2. By supplying a part of the steam to the steam injector 31A-2, the pool water in the pressure suppression chamber 14 is sucked into the steam injector 31A-2, discharged to the water mixing pipe 44, and supplied to the water supply pipe 33. Is done.

  Depends on the size of the interface between steam and water sucked during discharge. In the present embodiment, a branch steam supply pipe 43 is provided, and the steam injectors 31A-1 and 31A-2 are pressurized by causing the steam injector 31A-2 to suck the pool water in the pressure suppression chamber 14 from the branch steam supply pipe 43. Since the pool water in the suppression chamber 14 can be simultaneously sucked in, the interface between the steam supplied to the pressure suppression chamber 14 and the pool water can be increased. Therefore, according to this embodiment, since the flow rate of pool water discharged from one pressure suppression chamber 14 can be increased, the amount of water injected into the reactor pressure vessel 11 can be increased. Thereby, pool water can be supplied and circulated to the reactor pressure vessel 11 more efficiently.

(Fourth embodiment)
A heat removal apparatus according to a fourth embodiment will be described with reference to the drawings. In addition, the same code | symbol is attached | subjected to the member which has the same function as the said embodiment, and detailed description is abbreviate | omitted. FIG. 6 is a diagram illustrating a configuration of a nuclear reactor facility to which the heat removal apparatus according to the fourth embodiment is applied. As shown in FIG. 6, the heat removal apparatus 15D of the nuclear reactor facility 10D includes an auxiliary steam injector 51 and a bleed pipe 52 in the heat removal apparatus 15A of the first embodiment shown in FIG.

  The auxiliary steam injector 51 is provided in the water supply pipe 33. The auxiliary steam injector 51 has the same configuration as that of the steam injector 31A, and thus the description thereof is omitted.

  The extraction pipe 52 connects the reactor pressure vessel 11 and the auxiliary steam injector 51, and supplies steam from the reactor pressure vessel 11 to the auxiliary steam injector 51. As shown in FIG. 7, pool water W <b> 2 is supplied from the water supply pipe 33 to the auxiliary steam injector 51. When the pool water W2 is supplied from the water supply pipe 33 to the auxiliary steam injector 51, the steam taken out from the reactor pressure vessel 11 is supplied to the auxiliary steam injector 51 through the extraction pipe 52. The steam supplied to the auxiliary steam injector 51 is ejected from the tip of the extraction pipe 52 and flows into the auxiliary steam injector 51. The steam ejected from the nozzle tip of the extraction pipe 52 is mixed with the pool water W <b> 2 supplied from the water supply pipe 33. At this time, the steam is rapidly cooled and condensed by the pool water W2, and its volume is greatly reduced. Therefore, a space is generated in the auxiliary steam injector 51 as the steam is condensed, and a negative pressure is generated inside the mixing unit 37. Pool water W2 is sucked into the space generated by the condensation of the steam. Further, the flow rate of the steam introduced into the auxiliary steam injector 51 is increased by the negative pressure generated in the mixing unit 37, and the flow rate of the pool water W2 supplied from the water supply pipe 33 is further increased. Then, the pool water W2 has the highest flow velocity when passing through the throat portion 38, is decelerated and boosted from the diffuser portion 39 to the discharge port 31b, and is discharged from the discharge port 31b as pool water W3. The pool water W3 has a higher pressure than the pool water W2 flowing into the auxiliary steam injector 51, and is supplied to the reactor pressure vessel 11 through the water supply pipe 33.

  Therefore, when the steam is supplied to the extraction pipe 52, the discharge pressure of the pool water W2 discharged from the extraction pipe 52 becomes higher. Therefore, when the pool water W2 is poured into the reactor pressure vessel 11 for cooling. It can be used as a drive source.

  There is a possibility that the pressure in the reactor pressure vessel 11 becomes high due to a nuclear accident such as LOCA in the reactor facility 10, and the normal pressure pool water W2 may not be able to inject water into the reactor pressure vessel 11. is there. As such a situation where water cannot be injected into the reactor pressure vessel 11, for example, when the pressure drops before the steam reaches the pressure suppression chamber 14 from the reactor pressure vessel 11, or from the pressure suppression chamber 14 to the reactor. In some cases, the pressure decreases in the flow path for supplying the pool water W2 to the pressure vessel 11, and the driving force for injecting water into the reactor pressure vessel 11 is insufficient.

  According to the present embodiment, the pressure of the pool water W2 flowing through the water supply pipe 33 by the auxiliary steam injector 51 can be raised by the steam supplied from the extraction pipe 52, and therefore the high-pressure pool water is generated by the reactor pressure vessel 11. W2 can be supplied. Therefore, even when the pressure in the reactor pressure vessel 11 becomes high and water cannot be injected with the normal pressure pool water W2, water can be injected into the reactor pressure vessel 11, and power can be used more stably. The pool water can be supplied to the reactor pressure vessel 11 and circulated.

(Fifth embodiment)
A heat removal apparatus according to a fifth embodiment will be described with reference to the drawings. In addition, the same code | symbol is attached | subjected to the member which has the same function as the said embodiment, and detailed description is abbreviate | omitted. FIG. 8 is a diagram illustrating a configuration of a nuclear reactor facility to which the heat removal apparatus according to the fifth embodiment is applied. As shown in FIG. 8, the heat removal device 15E of the nuclear reactor facility 10E includes a coolant circulation passage 61 and an auxiliary heat exchanger 62 in the heat removal device 15A of the first embodiment shown in FIG.

  The coolant circulation passage 61 is provided so as to pass through the heat exchanger 16, and the coolant 63 is circulated. The coolant 63 only needs to be able to cool the pool water W2, and water or the like may be used.

  The auxiliary heat exchanger 62 is provided in the coolant circulation passage 61 in the reactor containment vessel 12, and the coolant 63 and the pool water W <b> 2 are indirectly heat-exchanged in the auxiliary heat exchanger 62. The auxiliary heat exchanger 62 is not limited to being installed in the reactor containment vessel 12 and may be provided outside the reactor containment vessel 12.

  The coolant 63 cooled by the heat exchanger 16 is sent to the auxiliary heat exchanger 62 through the coolant circulation passage 61, and indirectly heats the pool water W2 passing through the water injection pipe 32 in the auxiliary heat exchanger 62. Exchanged. The coolant 63 heat-exchanged and heated by the auxiliary heat exchanger 62 is sent to the heat exchanger 16 through the coolant circulation passage 61 and cooled again. As described above, the coolant 63 circulates in the coolant circulation passage 61. In addition, the pool water W <b> 2 cooled in the auxiliary heat exchanger 62 is sent to the reactor pressure vessel 11.

  The pool water W2 is water generated by condensing steam released from the reactor pressure vessel 11, and this steam is generated by a reaction between water and the core melt when the core melt is cooled with water. It has occurred. For this reason, the steam released from the reactor pressure vessel 11 contains radioactive substances and is contaminated. On the other hand, since the coolant 63 circulating in the coolant circulation passage 61 is only indirectly heat-exchanged with the pool water W2 in the auxiliary heat exchanger 62, it is not contaminated by radioactive materials. .

  Therefore, according to the present embodiment, it is possible to supply only the cooled pool water W2 to the reactor pressure vessel 11 while circulating the contaminated pool water W2 and the uncontaminated coolant 63 separately. Therefore, the heat exchanger 16 and the like can be continuously operated in a safer state without being contaminated with the pool water W2.

  As mentioned above, although several embodiment of this invention was described, these embodiment is shown as an example and is not intending limiting the range of invention. These novel embodiments can be implemented in various other forms, and various combinations, omissions, replacements, changes, and the like can be made without departing from the scope of the invention. These embodiments and modifications thereof are included in the scope and gist of the invention, and are included in the invention described in the claims and the equivalents thereof.

  DESCRIPTION OF SYMBOLS 10A-10E ... Reactor equipment, 11 ... Reactor pressure vessel, 12 ... Reactor containment vessel, 13 ... Vent pipe, 14 ... Pressure suppression room, 15A-15E ... Heat removal apparatus, 16 ... Heat exchanger (Heat exchange part) ), 21 ... core, 22 ... dry well, 23 ... main steam pipe, 24 ... main steam relief safety valve, 25 ... relief safety valve discharge pipe, 31A, 31A-1, 31A-2, 31B ... steam injector, 32A, 32B ... Steam supply pipe, 33 ... Water supply pipe, 34 ... Discharge valve, 35 ... Nozzle part, 36 ... Introduction part, 37 ... Mixing part, 38 ... Throat part, 39 ... Diffuser part, 41 ... Water conduit, 43 ... Branch steam supply Pipe 44, water mixing pipe 51 ... auxiliary steam injector 52 ... bleed pipe 61 ... coolant circulation passage 62 ... auxiliary heat exchanger 63 ... coolant, W1, W2 ... pool water.

Claims (7)

A heat removal device used in a nuclear reactor facility comprising a nuclear reactor containment vessel containing a reactor pressure vessel and a pressure suppression chamber containing pool water for condensing steam released into the reactor containment vessel There,
A steam supply pipe configured to be able to supply the steam inside the reactor containment vessel;
A nozzle section to which the pool water is supplied, a throat section, and a diffuser section; the steam from the steam supply pipe is supplied to the throat section at the nozzle section; and the pool is provided downstream of the diffuser section. A steam injector configured to discharge water;
A water supply pipe connecting the steam injector and the reactor pressure vessel;
A heat removal apparatus comprising:   The heat removal apparatus according to claim 1, wherein the nozzle portion of the steam injector is provided in the pool water in the pressure suppression chamber. The steam injector is provided outside the pressure suppression chamber;
The heat removal apparatus according to claim 1, further comprising a water conduit that is connected to a bottom portion of the pressure suppression chamber and supplies the pool water in the pressure suppression chamber to the steam injector. A plurality of said steam injectors;
A branched steam supply pipe branched from the steam supply pipe and supplying a part of the steam in the steam supply pipe to any of the steam injectors;
The heat removal apparatus according to any one of claims 1 to 3, further comprising a water mixing pipe that supplies pool water discharged from the steam injector to the water supply pipe. An auxiliary steam injector provided in the water supply pipe;
A bleed pipe for supplying the steam in the reactor pressure vessel from the reactor pressure vessel to the auxiliary steam injector;
The heat removal apparatus according to any one of claims 1 to 4, comprising: A coolant circulation path through which the coolant circulates;
A cooling unit provided in the coolant circulation passage for cooling the coolant;
A heat exchanging unit that is provided in the water supply pipe, heat-exchanges the pool water supplied to the reactor pressure vessel and the coolant, and cools the pool water;
The heat removal apparatus according to any one of claims 1 to 5, further comprising: A reactor containment that houses the reactor pressure vessel;
A pressure suppression chamber containing pool water for condensing steam supplied from the reactor containment vessel;
A heat removal device according to any one of claims 1 to 6,
A nuclear reactor facility comprising:

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