JP2005345158A - Boiling water reactor installation and method for renewing it - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide a method for renewing a boiling water reactor installation which improves the performance of a plant as well as enhances the safety of it and the installation. <P>SOLUTION: The boiling water reactor installation in this invention is so constituted that an internal pump 25 which changes the circulation of reactor water from an external circulation structure method to an internal circulation structure method is placed in a downcomer 22 of a reactor pressure vessel 20 during its renewal. <P>COPYRIGHT: (C)2006,JPO&NCIPI

Description

  The present invention relates to a method for renewing a boiling water reactor facility and a boiling water reactor facility, and in particular, when considering renewal due to the soundness and life of a reactor pressure vessel, a reactor internal structure and its ancillary equipment, The present invention relates to a boiling water reactor facility renewal method and a boiling water reactor facility which have been improved in order to further enhance safety and further improve performance.

  For example, in a nuclear power plant, with the aging of the boiling water reactor equipment over many years, the renewal time and countermeasures have been studied, and one of them is shown in FIG. 19, for example.

  FIG. 19 is a conceptual diagram showing a boiling water reactor facility of a type having a recirculation system that is a subject of update.

  In this boiling water reactor facility, a large number of fuel assemblies are loaded on a core 9 of a cylindrical long cylindrical reactor pressure vessel 4 and the lower end portions of these fuel assemblies are supported by a core support plate 10. The upper end is supported by the upper lattice plate 11.

  The core support plate 10 and the upper lattice plate 11 are fixed to a cylindrical core shroud 8 surrounding the core 9, and the core shroud 8 is fixed to the lower mirror part of the reactor pressure vessel 4 through a shroud support or the like. Has been.

  Further, a shroud head including a stand pipe and a steam / water separator 7 is provided on the upper portion of the core shroud 8, and a steam dryer 12 is further provided above the shroud head.

  On the other hand, a downcomer (annular space) 1 is formed in the lower part of the reactor pressure vessel 4 between the core shroud 8, the shroud support, and the reactor pressure vessel 4. ) Is circulated so as to be supplied to the core 9 from the lower part of the core shroud 8.

  The reactor recirculation unit 13 accommodates a jet pump 5 in the reactor pressure vessel 4, extends a recirculation pipe 2 provided with a recirculation pump 3 outside the reactor pressure vessel 4, and extends from the downcomer 1 side. The sucked reactor water (coolant) is supplied to the jet pump 5 through the recirculation pump 3 of the recirculation pipe 2, and from here, the core 9 is supplied to the core 9 through the lower part of the core shroud 8 using the attractive force of the jet. It is configured to supply water (cooling water).

  In the boiling water nuclear reactor facility having such a configuration, the reactor water supplied to the fuel assembly of the core 9 generates steam by the heat generated from the fuel assembly, and the generated steam is separated into steam and water. The steam is separated in the vessel 7 and supplied to the steam turbine (not shown) as dry steam in the steam dryer 12, and the turbine exhaust after the expansion work is condensed in the condenser (not shown), and then the water supply pipe 6. Return to reactor pressure vessel 4 via feed water sparger 14.

  In this way, in a boiling water reactor facility having an internal pump as opposed to a boiling water reactor facility having a recirculation system equipped with a jet pump 5, as shown in FIG. The internal pump 15 is installed, and the reactor recirculation unit 13 is removed along with the installation of the internal pump 15 to avoid a piping system breakage accident, and even if the reactor water (coolant) decreases, the core 9 It is configured to ensure that it is flooded and maintained.

  In recent boiling water reactor facilities, a plan for improved maintenance is currently being discussed. Based on this discussion, for example, JP 2002-341090 (Patent Document 1), JP 2002-3111195 ( Patent Document 2), Japanese Patent Application Laid-Open No. 2000-180577 (Patent Document 3), Japanese Patent Application Laid-Open No. 2000-346993 (Patent Document 4), Japanese Patent Application Laid-Open No. 9-145882 (Patent Document 5), Japanese Patent Application Laid-Open No. 8-285997. (Patent Document 6), Japanese Patent Application Laid-Open No. 8-62369 (Patent Document 7), Japanese Patent Application Laid-Open No. 8-62368 (Patent Document 8), Japanese Patent No. 3435270 (Patent Document 9) and Japanese Patent No. 3343447 ( Many inventions such as Patent Document 10) are disclosed.

Many of these inventions are centered on the technology to carry the same furnace-type equipment into and out of the building on the premise of the design concept at the time of construction.
JP 2002-341090 A JP 2002-3111195 A JP 2000-180577 A JP 2000-346993 A Japanese Patent Laid-Open No. 9-145882 JP-A-8-285997 JP-A-8-62369 JP-A-8-62368 , Japanese Patent No. 3435270 And Japanese Patent No. 3343447

  The technologies disclosed in Patent Literature 1 to Patent Literature 10 have the same boiling water reactor type as the initial construction of the boiling water reactor equipment to be renewed, and mainly focus on the replacement method of the reactor pressure vessel. .

  On the other hand, the future boiling water reactor equipment is not limited to the conventional design philosophy, even though the equipment is renewed, and it is possible to further enhance safety, thereby extending the plant life, and even further. Improvement of plant performance is desired.

  The present invention has been made based on such a background, and in combination with further enhancement of plant safety, a method for renewing boiling water reactor equipment that further improves plant performance. And to provide a boiling water reactor facility.

  In order to achieve the above object, a method for renewing a boiling water reactor facility according to the present invention includes a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel as described in claim 1. In the method for renewing a boiling water reactor facility in which the reactor water is steamed by heat generated from a core surrounded by a core shroud, the reactor water is circulated externally. This is a method of updating by changing from the circulation structure method to the internal circulation structure method.

  Moreover, in order to achieve the above-mentioned object, the method for renewing a boiling water reactor facility according to the present invention changes the reactor water circulation from an external circulation structure method to an internal circulation structure method. This is a method of removing the reactor recirculation unit and installing an internal pump when updating the system.

  Moreover, in order to achieve the above-described object, the method for renewing a boiling water reactor facility according to the present invention has secured the space by removing the core shroud as described in claim 3. In this method, an internal pump and a reactor water tube connected to the internal pump are provided in the space, and the circulation of the reactor water is changed from an external circulation structure method to an internal circulation structure method.

  Moreover, in order to achieve the above object, the boiling water reactor facility according to the present invention loads a fuel assembly into a reactor pressure vessel accommodated in a reactor containment vessel as described in claim 4. In a boiling water reactor facility configured to convert reactor water into steam by heat generated from the core, the reactor water is circulated from an external circulation structure system when the reactor pressure vessel is updated. An internal pump to be changed to the internal circulation structure system is installed in the downcomer of the reactor pressure vessel.

  Moreover, in order to achieve the above-mentioned object, the boiling water reactor facility according to the present invention does not have a core shroud when the reactor pressure vessel is updated as described in claim 5. While having a core shroudless structure, a reactor water tube is provided in series with the internal pump.

  Further, in order to achieve the above-described object, the boiling water reactor facility according to the present invention has a core of a core shroudless structure loaded with a fuel assembly in a space portion as described in claim 6. The spent fuel is loaded on the outermost peripheral side of the core.

  Moreover, in order to achieve the above object, the boiling water reactor facility according to the present invention measures the flow rate of the reactor water circulating in the reactor as described in claim 7. A flow meter measuring device is provided.

  Moreover, in order to achieve the above-described object, the boiling water reactor facility according to the present invention includes, as described in claim 8, a flowmeter measuring device, a venturi tube provided in a reactor water tube, A flow meter for measuring the flow rate of the reactor water flowing through the venturi tube and an addition flow meter for measuring the total flow rate corresponding to the number of the reactor water tubes.

  Moreover, in order to achieve the above-mentioned object, the boiling water reactor facility according to the present invention provides a water supply pipe for the reactor pressure vessel when the reactor pressure vessel is updated as described in claim 9. A flow meter measuring device is provided, and when the water supply is overflowed, a trip command or a runback command is given to the internal pump drive device of the internal pump, while a scram command or a control rod drive hydraulic system for driving the fuel rod is given. A transient event mitigation control device that provides a selection control rod insertion command is provided.

  Moreover, in order to achieve the above-described object, the boiling water reactor facility according to the present invention provides a transient event mitigation control device that performs a calculation based on a measured feed water flow signal. When the calculation signal of this transmitter exceeds a preset set value, the control rod drive hydraulic pressure that drives the fuel rod while giving a trip command or runback command to the internal pump drive device that drives the internal pump It is equipped with a flow switch that gives a scram command or selection control rod insertion command to the system.

  Moreover, in order to achieve the above object, the boiling water reactor facility according to the present invention has a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel as described in claim 11. In a boiling water reactor facility equipped with a loaded core and configured to steam the reactor water with the heat generated from the core, the reactor water in the reactor pressure vessel is extracted when the reactor pressure vessel is updated. And a low-pressure water injection system that draws pool water from the suppression pool and supplies it to the shutdown system.

  Moreover, in order to achieve the above-described object, the boiling water reactor facility according to the present invention includes, as described in claim 12, the shutdown system includes reactor water in the reactor pressure vessel and pool water in the suppression pool. A shutdown low-pressure water injection switching valve is provided.

  Moreover, in order to achieve the above object, the boiling water reactor facility according to the present invention has a fuel assembly in a reactor pressure vessel accommodated in a reactor containment vessel as described in claim 13. In a boiling water reactor facility comprising a loaded core and configured to steam the reactor water by heat generated from the core, when the reactor pressure vessel is updated, the pool water of the suppression pool is extracted and the containment vessel And a reactor core low-pressure water injection system for supplying the extracted pool water branched from the containment vessel spray system to the reactor pressure vessel.

  Moreover, in order to achieve the above object, the boiling water reactor facility according to the present invention has a fuel assembly in a reactor pressure vessel accommodated in a reactor containment vessel as described in claim 14. In a boiling water nuclear reactor facility equipped with a loaded core and configured to convert reactor water into steam by heat generated from the core, condensate from a condensate storage tank is transferred into the core when the reactor pressure vessel is updated. A control rod drive hydraulic system that supplies a control rod drive hydraulic pressure control unit that is a drive source of a control rod drive mechanism that drives a control rod inserted into the control rod, and the condensate storage tank that branches from the control rod drive hydraulic system The reactor is provided with a core high-pressure water spray system for supplying the condensate from the reactor to the reactor pressure vessel.

  Moreover, in order to achieve the above-mentioned object, the boiling water reactor facility according to the present invention has a fuel assembly in a reactor pressure vessel accommodated in a reactor containment vessel as described in claim 15. In a boiling water reactor facility comprising a loaded core and configured to convert reactor water into steam by heat generated from the core, among the pump and the cooling water injection valve provided in the cooling system for reactor isolation, the pump When the reactor water level in the reactor pressure vessel is low, the reactor water level meter for the pump drive that gives a start command based on the detected water level signal, and the reactor water level in the reactor pressure vessel in the cooling water injection valve When the temperature is low, a reactor water level gauge for a cooling water injection valve that gives a valve opening command based on the detected water level signal is provided.

  Moreover, in order to achieve the above object, the boiling water reactor facility according to the present invention has a fuel assembly in a reactor pressure vessel accommodated in a reactor containment vessel as described in claim 16. In a boiling water reactor facility comprising a loaded core and configured to steam the reactor water with heat generated from the core, the high-pressure cooling water from the high-pressure cooling water tank is supplied to the atomic reactor when the reactor pressure vessel is updated. A reactor cooling water supply system that supplies a reactor pressure vessel and a high pressure gas supply system that supplies a high pressure gas to the high pressure cooling water tank and applies a pressing force to the water surface of the high pressure cooling water tank are provided.

  In order to achieve the above object, the boiling water reactor facility according to the present invention provides a reactor coolant supply system from a high-pressure coolant tank to a reactor pressure vessel. A high-pressure cooling water supply pipe for supplying high-pressure cooling water is provided with a high-pressure cooling water supply valve, a steam relief valve is provided in the reactor pressure vessel, and when the reactor power of the reactor pressure vessel becomes high, the steam relief While the valve is opened to blow the steam in the furnace outside the system, the high-pressure cooling water supply valve is opened based on the valve opening signal of the steam relief valve.

  Further, in order to achieve the above object, the boiling water reactor facility according to the present invention has a high-pressure gas supply system in which a high-pressure gas is supplied from a high-pressure gas supply cylinder to a high-pressure cooling water tank. The high-pressure gas supply pipe is provided with a high-pressure gas supply stop valve, the high-pressure cooling water tank is provided with a high-pressure gas relief valve and a water level detector, and the water level of the high-pressure cooling water tank is higher than a predetermined set value. When low, the high pressure gas relief valve is opened by a signal from a water level detector, and the high pressure gas in the high pressure cooling water tank is blown out of the system, while the high pressure gas relief valve The high-pressure gas supply stop valve and the high-pressure coolant supply valve provided in the high-pressure coolant supply pipe of the reactor coolant supply system are closed at the same time.

  Moreover, in order to achieve the above object, the boiling water reactor facility according to the present invention has a fuel assembly in a reactor pressure vessel accommodated in a reactor containment vessel as described in claim 19. In a boiling water reactor facility equipped with a loaded core and configured to convert the reactor water into steam by heat generated from the core, the steam extracted from the reactor pressure vessel is isolated when the reactor pressure vessel is updated. An isolation condenser system for supplying the condensed water to the condenser and returning the condensed water to the reactor pressure vessel; and an isolation condenser steam supply pipe of the isolation condenser system for branching and extracting the extracted steam from the reactor containment vessel It is equipped with a containment container spray system to be supplied inside.

  The method for renewing a boiling water reactor facility and a boiling water reactor facility according to the present invention is an interface that changes the circulation of reactor water from a conventional external circulation structure method to an internal circulation structure method when a reactor pressure vessel is renewed. Since the null pump is installed in the downcomer of the reactor pressure vessel, it is possible to eliminate the piping rupture accident of the external circulation structure, and to securely enhance the safety of the reactor pressure vessel during operation.

  Embodiments of a boiling water reactor facility updating method and a boiling water reactor facility according to the present invention will be described below with reference to the drawings and reference numerals attached to the drawings.

  1 and 3 are conceptual diagrams showing a boiling water reactor facility. FIG. 1 is a conceptual diagram showing a first embodiment of a boiling water reactor facility at the time of update according to the present invention, and FIG. 3 is a conceptual diagram showing a boiling water reactor facility at the beginning of construction. FIG. 1 and FIG. 3 are compared in order to clarify the improvement points at the time of renewal compared to the beginning of construction. Also, in both FIG. 1 and FIG. 3, the same reference numerals are assigned to the same components.

  The method for renewing a boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of renewal are loaded with a large number of fuel assemblies in a core 23 of a cylindrical reactor pressure vessel 20, and these fuel assemblies The lower end portion of the body is supported by the core support plate 26, and the upper end portion is supported by the upper lattice plate 27.

  The core support plate 26 and the upper lattice plate 27 are fixed to a cylindrical core shroud 21 surrounding the core 23, and the core shroud 21 is fixed to the lower mirror portion of the reactor pressure vessel 20 via a shroud support or the like. I am letting.

  Further, a shroud head including a stand pipe and a steam / water separator 28 is provided on the upper portion of the core shroud 21, and a steam dryer 29 is further provided above the shroud head.

  The above-described components are the same as the components of the boiling water reactor facility of the type having the recirculation system at the beginning of construction, so only the same reference numerals are given, and redundant description is omitted.

  On the other hand, the boiling water reactor equipment at the time of renewal is a reactor in a downcomer (annular space) 22 formed below the reactor pressure vessel 20 and formed between the core shroud 21, the shroud support, and the reactor pressure vessel 20. A reactor water circulation section 24 that circulates water (coolant) and supplies the coolant from the lower portion of the reactor core shroud 21 toward the reactor core 23 is provided.

  The reactor water circulation section 24 is specifically an internal pump 25. As shown in FIG. 2, for example, three internal pumps 25a, 25b, and 25c are installed in the downcomer 22, and each internal pump 25a is installed. , 25b, 25c, the reactor water (coolant) is supplied from the lower part of the core shroud 21 toward the core 22.

  The reactor water that has received heat from the core 22 is supplied as saturated steam to the steam separator 28 shown in FIG. 1, where it is separated into moisture and steam, and further dried to dry steam by the steam dryer 29. And supplied to a steam turbine (not shown).

  In addition, the turbine exhaust that has finished the expansion work in the steam turbine is condensed in a condensate passage (not shown) to become condensate, and the pressure is raised and the temperature is increased to supply water as a water supply pipe 30 and a water supply sparger 31 as reactor water (coolant). To the reactor pressure vessel 20.

  On the other hand, a boiling water reactor of the type having a recirculation system at the beginning of construction is a jet pump that houses a reactor recirculation unit 24 in a reactor pressure vessel 20 as shown in FIGS. 32 and a recirculation pipe 34 having a recirculation pump 33 extending outside the reactor pressure vessel 20, and the reactor water sucked from the downcomer 22 is jet pumped through the recirculation pump 33 of the recirculation pipe 34. 32 is supplied to the core 23 from the lower part of the core shroud 21 by using the action of a jet.

  As described above, the method for renewing a boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of renewal change the reactor water circulation method from the inside of the reactor pressure vessel 20 to the outside of the reactor. Since the internal pump 25 that changes the external circulation structure system having the reactor recirculation system to the internal circulation structure system that circulates inside the vessel is installed in the downcomer 22, the piping breakage accident of the external circulation structure is eliminated. Therefore, safety during operation of the reactor pressure vessel 20 can be surely enhanced.

  In addition, the method for renewing the boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of renewal are configured so that the circulation of the reactor water has an internal circulation structure and a sufficient space area is ensured. More fuel assemblies can be loaded in the secured space area, and as a result, the reactor power can be improved and the plant thermal efficiency can be improved as more fuel assemblies are loaded.

  FIG. 5: is a conceptual diagram which shows 2nd Embodiment of the update method of the boiling water reactor equipment which concerns on this invention, and the boiling water reactor equipment at the time of update.

  The method for renewing a boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of renewal are such that the reactor water is circulated in a downcomer 22 located in the lower part of the reactor pressure vessel 20 in the vessel. A pump 25 is installed, and a cylindrical reactor water tube (RIP tube) 35 that guides and circulates reactor water (coolant) is connected to the internal pump 25.

  In addition, the method for renewing a boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of renewal provide reactor water (coolant) to be guided to the internal pump 25 via a reactor water tube 35. When supplying to the core 23, as shown in FIG. 6, it is set as what is called a core shroudless structure which abbreviate | omitted installation of the core shroud.

  As described above, the method for updating the boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of the update include the reactor water tube 35 that is connected to the internal pump 25 installed in the downcomer 22. At the same time, since the core 23 including a large number of fuel rods has a core shroudless structure so as to ensure a relatively wide space, it is possible to more easily perform the operation of attaching peripheral peripheral equipment.

FIG. 7 is a plan view showing a third embodiment of the boiling water reactor facility renewal method and boiling water reactor facility at the time of renewal according to the present invention. The renewal method and the boiling water reactor equipment at the time of renewal are the reactor water tubes 35a, 35b, 35c connected to the internal pump installed in the downcomer 22 of the reactor pressure vessel 20, as in the second embodiment. The core 23 provided with a fuel rod assembly 35 is provided with a core shroud structure having no core shroud so as to ensure a large space area of the downcomer 22 while securing a wide space area as shown in FIG. A large number of fuel assemblies 36 are loaded in the regions A ₁ , A ₂ ,... Indicated by broken lines, and the spent fuel 37 is loaded as blankets on the outer peripheral side hatched portion.

As described above, the method for renewing the boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of renewal are the cylindrical reactor water tube 35a that is connected to the internal pump installed in the downcomer 22. , 35b, 35c, and 35d, and the core 25 loaded with the fuel assembly 36 has a core shroudless structure, and a wide space area is secured by the downcomer 22, while the area A ₁ , Since many fuel assemblies 36 and spent fuel 37 are loaded by A ₂ ,..., The reactor power (heat output) of the core 23 can be increased and the plant thermal efficiency can be improved.

  In addition, the method for updating the boiling water reactor facility according to the present embodiment and the boiling water reactor facility at the time of the update load a large number of fuel assemblies 36 on the downcomer 22 having a larger space area, Since the spent fuel 37 is loaded as a blanket on the outer peripheral side, it is possible to reduce the irradiation amount to the outside of the reactor pressure vessel 20 in combination with the high burnup, and to reduce the exposure amount of workers. It can be kept low.

  FIG. 9 is a conceptual diagram showing a fourth embodiment of the boiling water reactor facility at the time of update according to the present invention.

  The boiling water reactor facility at the time of renewal according to the present embodiment is connected to an internal pump 25 installed under the downcomer 22 formed between the reactor pressure vessel 20 and the core 23 for reactor water. A tube (RIP tube) 35 is provided, and a flow meter 39 for measuring the flow rate between the venturi tube 38 provided in the reactor water tube 35 and the inlet side thereof is provided, and further provided corresponding to the number of the venturi tubes 38. The additional flow meter 40 for adding the total flow rate of the flow meter 39 is provided.

  As described above, the boiling water reactor facility at the time of update according to the present embodiment includes the flow meter 39 in the venturi tube 38 provided in the reactor water tube 35 and the flow meter corresponding to the number of the venturi tubes 38. Since the addition flow meter 40 for adding the total flow rate of 39 is provided, the flow rate of the reactor water flowing through the reactor water tube 35 is accurately measured, and the safe design limit minimum limit output ratio is obtained under the accurate measurement of the reactor water flow rate. By setting (SLMCPR), the core design margin based on the relaxation of the thermal safety limit value can be expanded, and as a result, the thermal output can be increased.

  In the present embodiment, the flow meter 39 is used to measure the flow rate between the venturi tube 38 and the inlet side thereof. However, the present embodiment is not limited to this example. For example, as shown in FIG. 10 as the fifth embodiment, The flow rate between the venturi tube 38 and the upstream side of the reactor water tube 35 may be measured by a flow meter 39, and as shown in FIG. 11 as a sixth embodiment, the flow rate between the upstream side in the venturi tube 38 and The flow rate between the downstream side and the flow meter 39 may be measured.

  FIG. 12: is a conceptual diagram which shows 7th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention.

  In the boiling water reactor facility at the time of renewal according to the present embodiment, when the feed water flows into the feed water pipe 30 or the feed water sparger 31 for some reason, the fluctuation of the heat output generated from the reactor core 23 becomes severe. In consideration of the accompanying fluctuations in electrical output, a transient event mitigation control device 41 is provided to suppress the thermal output fluctuations of the core 23.

  The transient event mitigation control device 41 includes a flow meter 43 that measures the flow rate of feed water that flows through a flow meter measurement device 42 such as a venturi pipe provided in the feed water pipe 30 on the upstream side of the feed water scrubber 31, and a flow meter 43. A transmitter 44 for calculating the measured signal, and when the signal calculated by the transmitter 44 exceeds a predetermined set value, the trip signal a or the runback signal b is given to the internal pump driving device 47 of the internal pump 25. In addition, a flow switch 45 for supplying a scram signal c or a selective control rod insertion signal d to the control rod drive hydraulic system 46 is provided to reduce the core flow rate by the internal pump 25 and to the reactor by the control rod drive hydraulic system 46 to the reactor. Or a control rod is selectively inserted to reduce the furnace output. In addition, since the other component is the same as the component of 2nd Embodiment, the same code | symbol is attached | subjected and duplication description is abbreviate | omitted.

  Thus, this embodiment is provided with the transient event relaxation control device 41 in the water supply pipe 30 on the upstream side of the water supply sparger 31, and when the water supply supplied to the reactor pressure vessel 20 becomes an excessive flow rate for some reason, Since the trip or runback signal is given to the internal pump drive device 47 of the internal pump 25 and the scram or selection control insertion signal is given to the control rod drive hydraulic system 46, the core 23 can be operated stably. it can.

  FIG. 13: is a conceptual diagram which shows 8th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention.

  In the boiling water reactor facility at the time of renewal according to the present embodiment, when the reactor power from the reactor pressure vessel 20 increases with the renewal, the water source securing has been strengthened so that more cooling water can be supplied to the core. Therefore, the shutdown system (cooling system when the reactor is shut down) 48 is combined with the low-pressure water injection system 50 using the pool water of the suppression pool 49 as a water source.

  The shutdown system 48 supplies reactor water (coolant) of the reactor pressure vessel 20 as cooling water for the reactor core, and a shutdown suction pipe having shutdown suction isolation valves 51a and 51b and a shutdown low-pressure water injection switching valve 52 provided on the way. 53 and a shutdown low pressure water injection pipe 58 which is connected to one end on the downstream side of the shutdown low pressure water injection switching valve 52 and includes a pump 54, a heat exchanger 55, a cooling water injection valve 56 and a check valve 57 in the middle. The shutdown low-pressure water injection combined system 59 and the low-pressure water injection pipe branched from the other downstream end of the shutdown low-pressure water injection switching valve 52 and connected to the suppression pool 49 via the suppression pool water suction isolation valve 60 in the middle The low-pressure water injection system 50 provided with 61 is comprised.

  Further, the shutdown system 48 branches from the outlet side of the heat exchanger 55 of the shutdown low-pressure water injection and combined system 59, and a test system 64 including a test pipe 63 that is connected to the suppression pool 49 via the test valve 62 in the middle. During the test, the pool water of the suppression pool 49 is circulated to check the operation of the test valve 62 and the like.

  Further, the shutdown system 48 includes a control system 65, and the reactor detected from the reactor water level meter 66 of the control system 65 when the reactor power of the reactor pressure vessel 20 increases for some reason and the water level of the reactor water becomes low. Based on the water level signal, the pump 54 is automatically activated, the cooling water injection valve 56 is opened and closed, and the test valve 62 is opened and closed.

  As described above, in this embodiment, when the reactor output of the reactor pressure vessel 20 increases for some reason, the shutdown system 48 that supplies cooling water to the core of the reactor pressure vessel 20 using a part of the reactor water. In addition, a low-pressure water injection system 50 for supplying cooling water to the core of the reactor pressure vessel 20 using the pool water of the suppression pool 49 is combined to strengthen the supply of cooling water to the reactor pressure vessel 20 core. The core of the reactor pressure vessel 20 can be made to operate stably, and thus the life of the plant based on the stable operation of the core can be extended.

  FIG. 14: is a conceptual diagram which shows 9th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention.

  The boiling water reactor facility at the time of renewal according to the present embodiment uses the pool water of the suppression pool 49 in the event of an accident, supplies it as spray water to the containment vessel 66, and cools the containment vessel spray system 67 to be cooled to the containment vessel spray system 67. In addition to cooling the containment vessel 66, the water injection system 68 is combined to cool the core of the reactor pressure vessel 20 enclosed and contained in the containment vessel 66, thereby strengthening the securing of the core cooling water source for the reactor pressure vessel 20 It is a thing.

  A containment vessel spray system 67 supplies pool water from the suppression pool 49 to the containment vessel 66 as cooling water, and a containment vessel spray pipe 72 having a pump 69, a heat exchanger 70, and a containment vessel spray valve 71 interposed therebetween. I have.

  Further, the containment vessel spray system 67 branches from the inlet side of the containment vessel spray valve 71 and supplies cooling water to the core of the reactor pressure vessel 20 by interposing a cooling water injection valve 56 and a check valve 57 in the middle. A core low-pressure water injection system 68 provided with a core low-pressure water injection pipe 73 is provided.

  Further, the containment container spray system 67 includes a test pipe 75 that branches from the outlet side of the heat exchanger 70, circulates the pool water of the suppression pool 49 at the time of testing, and includes valves 74a and 74b in the middle. A test system 76 is provided.

  Further, the containment vessel spray system 67 includes a control system 77, and based on the reactor water level signal detected from the reactor water level meter 78 of the control system 77 when there is an accident in the containment vessel 66 or the reactor pressure vessel 20 due to some circumstances. Thus, the automatic start of the pump 69, the cooling water injection valve 56, and the containment container spray valve 71 are each given a valve opening command.

  As described above, in the present embodiment, when an accident occurs in the containment vessel 66 or the reactor pressure vessel 20 for some reason, the pool water of the suppression pool 49 is supplied to the containment vessel 66 as spray water to the containment vessel 66. Since the core low-pressure water injection system 68 that supplies the core water of the reactor pressure vessel 20 as cooling water using the pool water of the suppression pool 49 is combined, the supply of cooling water to the core of the reactor pressure vessel 20 has been strengthened. The core of the reactor pressure vessel 20 can be made to operate stably, and the life of the plant based on the stable operation of the core can be extended.

  FIG. 15: is a conceptual diagram which shows 10th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention.

  The boiling water reactor facility at the time of renewal according to the present embodiment is a control rod drive that serves as a drive source of a control rod drive mechanism 79 that drives a control rod inserted into a core accommodated in the reactor pressure vessel 20. A control rod drive water pressure system 83 provided with a control rod drive water pressure pipe 82 for supplying the condensate of the condensate storage tank 81 to the water pressure control unit 80 is combined with a core high-pressure water spray system 84 to drive the control rod drive mechanism 79. In addition, the core cooling water supply water source securing of the reactor pressure vessel 20 is strengthened.

  The core high-pressure water injection spray system 84 branches from the outlet side of the condensate pump 85 of the control rod drive water pressure system 83 and is connected to the reactor pressure vessel 20 via the core high-pressure water injection spray valve 86 on the way. A spray pipe 87 is provided, and when the thermal output of the core increases, a valve opening command is given to the core high-pressure water injection spray valve 86 based on a signal detected from the reactor water level meter 78 to suppress the thermal output of the core. .

  Thus, in this embodiment, the control rod drive hydraulic system 83 that supplies the condensate of the condensate storage tank 81 to the control rod drive hydraulic pressure control unit 80 that is the drive source of the control rod drive mechanism 79 of the reactor pressure vessel 20. And a core high-pressure water injection spray system 87 for supplying cooling spray water to the core of the reactor pressure vessel 20 by using the condensate in the condensate storage tank 81, and supplying cooling water supply water to the core of the reactor pressure vessel 20. Since the securing has been strengthened, the core of the reactor pressure vessel 20 can be operated stably, and the life of the plant based on the stable operation of the core can be extended.

  FIG. 16: is a conceptual diagram which shows 11th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention.

  The boiling water reactor facility at the time of renewal according to this embodiment includes a pump 90 and a cooling water injection valve 91 provided in a cooling water pipe 89 of a cooling system (RCIC) 88 for reactor isolation. When the reactor water level of the pressure vessel 20 is lower than a preset set water level, the reactor water level of the reactor pressure vessel 20 is set in advance to the pump activation reactor water level meter 92 and the cooling water injection valve 91 that give a startup signal. A cooling water injection valve reactor water level meter 93 for providing a valve opening signal when the set water level is lower than the set water level is provided.

  As described above, in this embodiment, when the reactor water level of the reactor pressure vessel 20 is lower than the preset set water level, the pump drive reactor water level meter 92 and the cooling water injection valve that gives the pump 90 a start command. Since the reactor water level meter 93 for cooling water injection valve which gives a valve opening command to 91 is provided, the pump 90 can be started earlier, the cooling water injection valve 91 can be opened earlier, and the reactor isolation cooling system ( Based on the earlier supply of cooling water from the RCIC 88 to the core, the core can be operated stably.

  FIG. 17 is a conceptual diagram showing a twelfth embodiment of the boiling water reactor facility at the time of update according to the present invention.

  The boiling water reactor facility at the time of update according to the present embodiment includes a reactor cooling water supply system 94 that supplies cooling water from the high pressure cooling water tank 95 to the core of the reactor pressure vessel 20, and a high pressure cooling water tank 95. A high-pressure gas supply system 96 that supplies high-pressure gas from the high-pressure gas cylinder 100 is provided.

  The reactor coolant supply system 94 includes high-pressure coolant supply valves 98a and 98b and a steam relief valve 99 in a high-pressure coolant supply pipe 97 that connects the reactor pressure vessel 20 and the high-pressure coolant tank 95 to each other. Is increased, the steam relief valve 99 is opened to blow the steam in the furnace outside the system, and the automatic decompression system (ADS, not shown) is operated based on the opening signal of the steam relief valve 99. The high-pressure cooling water supply valves 98a and 98b are opened by the calculation signal, and the high-pressure cooling water is supplied from the high-pressure cooling water tank 95 to the core of the reactor pressure vessel 20 through the high-pressure cooling water supply pipe 97. Yes.

  The high-pressure gas supply system 96 includes a high-pressure gas supply cylinder 100 that supplies a high-pressure gas to the high-pressure cooling water tank 95 and applies a pressing force to the water surface of the high-pressure cooling water. A high-pressure gas supply pipe 101 that connects the tanks 95 to each other includes a high-pressure gas supply stop valve 102 and a pressure adjustment valve 103 that adjusts the pressure of the high-pressure gas.

  The high-pressure gas supply system 96 includes a high-pressure cooling water tank 95 with a high-pressure gas relief valve 104 and a water level detector 105, and the high-pressure cooling water level in the high-pressure cooling water tank 95 becomes lower than a predetermined set value. The high-pressure gas in the high-pressure cooling water tank 95 is blown out of the system through the high-pressure gas relief valve 104 by a signal from the water level detector 105, and the automatic pressure reducing system (ADS) is based on the valve opening signal of the high-pressure gas relief valve 104. ), And the high-pressure gas supply stop valve 102 and the high-pressure cooling water supply valves 98a and 98b of the reactor cooling water supply system 94 are simultaneously closed by the calculation signal, and the high-pressure gas supply pipe 101 is connected to the high-pressure gas supply cylinder 100. The high pressure gas supply to the high pressure cooling water tank 95 is cut off via the high pressure cooling water tank 95 and the reactor core of the reactor pressure vessel 20 via the high pressure cooling water supply pipe 97. And a configuration sever the supply of high pressure cooling water.

  Thus, according to the present embodiment, when the reactor power of the reactor pressure vessel 20 becomes high, the steam relief valve 99 is opened, the steam in the reactor is blown out of the system, and the high pressure is based on the valve opening signal. A reactor water supply system 94 that opens the coolant water supply valves 98a and 98b and supplies high-pressure coolant from the high-pressure coolant tank 95 to the core of the reactor pressure vessel 20 through the high-pressure coolant supply pipe 97; While the high pressure gas is supplied from the high pressure gas supply cylinder 100 to the high pressure cooling water tank 95 via the high pressure gas supply pipe 101 and the water level of the high pressure cooling water tank 95 is being pressed, the water level becomes lower than the set value. In response to the signal from the water level detector 105, the high-pressure gas relief valve 104 is opened to blow the high-pressure gas in the high-pressure cooling water tank 95 out of the system, and the high-pressure gas supply stop valve 102 based on the valve-opening signal. And reactor A high-pressure gas supply system 96 that simultaneously closes the high-pressure cooling water supply valves 98a and 98b of the reject water supply system 94 is provided, and supply of high-pressure gas from the high-pressure gas supply cylinder 100 to the high-pressure cooling water tank 95 is cut off and high-pressure cooling is performed. The supply of the high-pressure cooling water from the water tank 95 to the reactor core of the reactor pressure vessel 20 is cut off. For example, for a short time until the low-pressure water injection system shown in FIGS. 94 has been started to strengthen the supply of cooling water to the reactor core of the reactor pressure vessel 20, so that the reactor core of the reactor pressure vessel 20 can be operated stably, and consequently the plant based on the stable operation of the reactor core can be operated. Life can be extended.

  FIG. 18 is a conceptual diagram showing a thirteenth embodiment of a boiling water reactor facility at the time of update according to the present invention.

  The boiling water reactor facility at the time of update according to the present embodiment combines the containment vessel spray system 107 and the suppression pool condensate water storage system 117 with the isolation condenser system 106, and after the operation of the reactor pressure vessel 20 is stopped, The heat removal function of the furnace containment vessel 66 is enhanced.

  The isolation capacitor system 106 supplies steam generated from the reactor pressure vessel 20 enclosed and accommodated in the reactor containment vessel 66 to the isolation capacitor 108, and the isolation capacitor steam supply isolation valves 109a and 109b are provided in the middle. The condensed condenser steam supply piping 110 and the condensed water condensed by the isolation condenser 108 are returned to the reactor pressure vessel 20, and the isolation condenser condensed water return isolation valves 111a and 111b are interposed on the way. An isolation condenser condensed water return pipe 112 is provided to provide a backup function to supply when the reactor water in the reactor pressure vessel 20 is low.

  In the isolation capacitor system 106 having such a configuration, the present embodiment branches from the isolation capacitor vapor supply pipe 110 and is connected to the reactor containment vessel 66 via the containment vessel inlet valves 113a and 113b on the way. Suppression that branches from the containment vessel spray system 107 including the containment vessel steam supply pipe 114 to be connected and the isolation condenser condensed water return pipe 112 and is connected to the suppression pool 49 via the condensed water return valves 115a and 115b on the way. A suppression pool condensate water storage system 117 having a pool condensate supply pipe 116 is used.

  Thus, in this embodiment, the containment vessel spray system 107 and the suppression pool condensate water storage system 117 are combined with the isolation condenser system 106, and the heat removal function of the containment vessel 66 is enhanced after the reactor pressure vessel 20 is shut down. Since it was set as the structure which carries out, the storage container 66 can be cooled earlier, a stop time can be shortened further, and an early restart can be coped with.

The conceptual diagram which shows 1st Embodiment of the update method of the boiling water reactor equipment which concerns on this invention, and the boiling water reactor equipment at the time of update. AA arrow direction cut | disconnection sectional drawing of FIG. The conceptual diagram which shows the boiling water reactor equipment of the beginning of construction. FIG. 4 is a cross-sectional view taken along the line B-B in FIG. The conceptual diagram which shows 2nd Embodiment of the update method of the boiling water reactor equipment which concerns on this invention, and the boiling water reactor equipment at the time of update. CC sectional view taken along the line CC of FIG. The top view which shows 3rd Embodiment of the update method of the boiling water reactor equipment which concerns on this invention, and the boiling water reactor equipment at the time of update. The top view which shows having loaded many fuel rods in the space of the core shown in FIG. 7, and having loaded the spent fuel on the outer peripheral side. The conceptual diagram which shows 4th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 5th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 6th Embodiment of the boiling water reactor facility at the time of the update which concerns on this invention. The conceptual diagram which shows 7th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 8th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 9th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 10th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 11th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 12th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows 13th Embodiment of the boiling water reactor equipment at the time of the update which concerns on this invention. The conceptual diagram which shows the conventional boiling water reactor equipment. The conceptual diagram which shows the conventional improved boiling water reactor equipment.

Explanation of symbols

  DESCRIPTION OF SYMBOLS 1 ... Downcomb, 2 ... Recirculation piping, 3 ... Recirculation pump, 4 ... Reactor pressure vessel, 5 ... Jet pump, 6 ... Feed water piping, 7 ... Gas-water separator, 8 ... Core shroud, 9 ... Core 10 DESCRIPTION OF SYMBOLS ... Core support plate, 11 ... Upper lattice plate, 12 ... Steam dryer, 13 ... Reactor recirculation part, 14 ... Feed water sparger, 15 ... Internal pump, 20 ... Reactor pressure vessel, 21 ... Core shroud, 22 ... Downcomb, 23 ... core, 24 ... reactor water circulation section, 25, 25a, 25b, 25c ... internal pump, 26 ... core support plate, 27 ... upper lattice plate, 28 ... gas / water separator, 29 ... steam dryer, 30 ... Water supply piping, 31 ... Water supply sparger, 32 ... Jet pump, 33 ... Recirculation pump, 34 ... Recirculation piping, 35, 35a, 35b, 35c, 35d ... Reactor water tube, 36 ... Fuel rod, 37 ... Used 38 ... Venturi tube 39 ... Flow meter 40 ... Additional flow meter 41 ... Transient event mitigation control device 42 ... Flow meter measurement device 43 ... Flow meter 44 ... Transmitter 45 ... Flow switch 46 ... Control Rod drive hydraulic system, 47 ... Internal pump drive device, 48 ... Shutdown system, 49 ... Suppression pool, 50 ... Low pressure injection system, 51a, 51b ... Shutdown suction isolation valve, 52 ... Shutdown low pressure injection switch, 53 ... Shutdown suction Piping, 54 ... Pump, 55 ... Heat exchanger, 56 ... Cooling water injection valve, 57 ... Check valve, 58 ... Shutdown low pressure injection combined use pipe, 59 ... Shutdown low pressure injection combined use system, 60 ... Suppression pool water suction isolation valve, 61 ... Low pressure water injection pipe, 62 ... Test valve, 63 ... Test pipe, 64 ... Test system, 65 ... Control system, 66 Reactor containment vessel, 67 ... containment vessel spray system, 68 ... core low pressure injection system, 69 ... pump, 70 ... heat exchanger, 71 ... containment vessel spray valve, 72 ... containment vessel spray pipe, 73 ... core low pressure injection pipe, 74a, 74b ... valve, 75 ... test piping, 76 ... test system, 77 ... control system, 78 ... reactor water level meter, 79 ... control rod drive mechanism, 80 ... control rod drive hydraulic control unit, 81 ... condensate storage tank, 82 ... Control rod drive hydraulic piping, 83 ... Control rod drive hydraulic system, 84 ... Core high-pressure water injection spray system, 85 ... Condensate pump, 86 ... Core high-pressure water injection spray system, 87 ... Core high-pressure water injection spray piping, 88 ... Nuclear reactor Isolation cooling system, 89 ... cooling pipe, 90 ... pump, 91 ... cooling water injection valve, 92 ... pump drive reactor water level meter, 93 ... cooling water injection valve reactor water level meter, 94 ... reactor cooling water supply Series, 95 ... high Pressure cooling water tank, 96 ... high pressure gas supply system, 97 ... high pressure cooling water supply piping, 98a, 98b ... high pressure cooling water supply valve, 99 ... steam relief valve, 100 ... high pressure gas supply cylinder, 101 ... high pressure gas supply piping, DESCRIPTION OF SYMBOLS 102 ... High pressure gas supply stop valve, 103 ... Pressure adjustment valve, 104 ... High pressure gas relief valve, 105 ... Water level detector, 106 ... Isolation capacitor system, 107 ... Containment container spray system, 108 ... Isolation capacitor, 109a, 109b ... Isolation condenser steam supply isolation valve, 110 ... Isolation condenser steam supply pipe, 111a, 111b ... Isolation condenser condensate return isolation valve, 112 ... Isolation condenser activation water return pipe, 113a, 113b ... Containment vessel inlet valve, 114. Containment vessel steam supply piping, 115a, 1 5b ... condensed water return valve, 116 ... suppression pool condensed water supply pipe, 117 ... suppression pool condensed water storage system.

Claims (19)

Boiling water for renewing boiling water reactor equipment that uses the fuel generated in the reactor pressure vessel contained in the reactor containment vessel and the reactor water is steamed by the heat generated from the core surrounded by the core shroud. A method of updating a boiling water reactor facility, wherein the circulation of the reactor water is updated by changing from an external circulation structure method to an internal circulation structure method. The boiling water mold according to claim 1, wherein when the reactor water circulation is updated by changing the external circulation structure method to the internal circulation structure method, the reactor recirculation unit is removed and an internal pump is installed. Renewal method for nuclear reactor equipment. The reactor core shroud is removed to secure a space, and an internal pump and a reactor water tube connected to the internal pump are provided in the secured space. The method of updating a boiling water reactor facility according to claim 2, wherein the updating is performed by changing to a structural system. In a boiling water reactor facility comprising a reactor core loaded with a fuel assembly in a reactor pressure vessel accommodated in a reactor containment vessel, and configured to convert reactor water into steam by heat generated from the reactor core, the reactor A boiling water type characterized in that an internal pump for changing the reactor water circulation from an external circulation structure method to an internal circulation structure method is installed in the downcomer of the reactor pressure vessel when the pressure vessel is updated. Reactor equipment. 5. The reactor pressure vessel is provided with a reactor water tube connected to the internal pump while the reactor core has a reactor core shroudless structure without a reactor core shroud when the reactor pressure vessel is updated. The boiling water reactor facility described. 6. The boiling water reactor according to claim 5, wherein the core having a core shroudless structure is configured such that a fuel assembly is loaded in a space portion and spent fuel is loaded on the outermost peripheral side of the core. Facility. 6. The boiling water reactor facility according to claim 5, wherein the reactor water tube is provided with a flow meter measuring device for measuring a flow rate of reactor water circulating in the reactor. The flow meter measuring device includes a venturi tube provided in the reactor water tube, a flow meter for measuring the flow rate of the reactor water flowing through the venturi tube, and an additional flow rate for measuring the total flow rate corresponding to the number of the reactor water tubes. The boiling water reactor facility according to claim 7, characterized by comprising: When the reactor pressure vessel is updated, a flow meter measurement device is provided in the water supply pipe of the reactor pressure vessel, and when the water supply is an excessive flow rate, a trip command or a runback command is sent to the internal pump drive device of the internal pump. 5. A boiling water reactor facility according to claim 4, further comprising a transient event mitigation control device for supplying a scram command or a selection control rod insertion command to a control rod drive hydraulic system for driving the fuel rod. The transient event mitigation control device trips to the transmitter that calculates based on the measured feed water flow signal and the internal pump drive that drives the internal pump when the calculated signal of the transmitter exceeds a preset value. 10. A boiling water reactor according to claim 9, further comprising a flow switch for giving a scram command or a selective control rod insertion command to a control rod drive hydraulic system for driving a fuel rod while giving a command or a runback command. Facility. In a boiling water reactor facility comprising a reactor core loaded with a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel and configured to convert reactor water into steam by heat generated from the reactor core, the reactor When the pressure vessel is renewed, a shutdown system for extracting and returning the reactor water in the reactor pressure vessel again, and a low-pressure water injection system for extracting pool water from the suppression pool and supplying the shutdown water to the shutdown system are provided. Boiling water reactor facility. The boiling water reactor facility according to claim 11, wherein the shutdown system includes a shutdown low-pressure water injection switching valve for switching between reactor water in the reactor pressure vessel and pool water in the suppression pool. In a boiling water reactor facility comprising a reactor core loaded with a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel and configured to convert reactor water into steam by heat generated from the reactor core, the reactor When renewing the pressure vessel, the storage vessel spray system for extracting the pool water from the suppression pool and supplying it to the containment vessel, and the branched water from the containment vessel spray system is supplied to the reactor pressure vessel. A boiling water reactor facility equipped with a core low-pressure water injection system. In a boiling water reactor facility comprising a reactor core loaded with a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel and configured to convert reactor water into steam by heat generated from the reactor core, the reactor Control rod drive water pressure that supplies the condensate from the condensate storage tank to the control rod drive water pressure controller unit that is the drive source of the control rod drive mechanism that drives the control rod inserted into the core when the pressure vessel is updated And a boiling water reactor facility comprising a core high-pressure water spray system that branches from the control rod drive hydraulic system and supplies the condensate from the condensate storage tank to the reactor pressure vessel . In a boiling water reactor facility equipped with a core loaded with a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel, the reactor water is steamed by the heat generated from the core. Among the pump and cooling water injection valve provided in the time cooling system, a pump drive reactor water level meter that gives a start command based on the detected water level signal when the reactor water level of the reactor pressure vessel is low The cooling water injection valve is provided with a reactor water level meter for a cooling water injection valve that gives a valve opening command based on a detected water level signal when the reactor water level of the reactor pressure vessel is low. Boiling water reactor equipment. In a boiling water reactor facility comprising a reactor core loaded with a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel and configured to convert reactor water into steam by heat generated from the reactor core, the reactor At the time of renewal of the pressure vessel, a reactor coolant supply system that supplies the reactor pressure vessel with high-pressure coolant from the high-pressure coolant tank, and a water surface of the high-pressure coolant tank by supplying high-pressure gas to the high-pressure coolant tank A boiling water reactor facility equipped with a high-pressure gas supply system that applies a pressing force to the water. The reactor coolant supply system includes a high-pressure coolant supply valve in a high-pressure coolant supply pipe for supplying high-pressure coolant from a high-pressure coolant tank to a reactor pressure vessel, and a steam relief valve in the reactor pressure vessel. When the reactor power of the reactor pressure vessel becomes high, the steam relief valve is opened to blow the steam inside the reactor out of the system, and the high pressure cooling water supply is performed based on the steam relief valve opening signal. 17. The boiling water reactor facility according to claim 16, wherein the valve is configured to open. The high pressure gas supply system includes a high pressure gas supply stop valve in a high pressure gas supply pipe for supplying high pressure gas from a high pressure gas supply cylinder to a high pressure cooling water tank, and a high pressure gas relief valve and a water level detector in the high pressure cooling water tank. And when the water level of the high-pressure cooling water tank becomes lower than a preset value, the high-pressure gas relief valve is opened by a signal from a water level detector, and the high-pressure gas in the high-pressure cooling water tank is A configuration in which the high-pressure gas supply stop valve and the high-pressure coolant supply valve provided in the high-pressure coolant supply pipe of the reactor coolant supply system are simultaneously closed based on the opening signal of the high-pressure gas relief valve while being blown outside The boiling water reactor facility according to claim 16, wherein In a boiling water reactor facility comprising a reactor core loaded with a fuel assembly in a reactor pressure vessel housed in a reactor containment vessel and configured to convert reactor water into steam by heat generated from the reactor core, the reactor When the pressure vessel is renewed, the steam extracted from the reactor pressure vessel is supplied to the isolation condenser to be condensed, and the condensed condenser system for returning the condensed water to the reactor pressure vessel, and the isolation condenser system A boiling water reactor facility comprising a containment vessel spray system that branches from an installation condenser steam supply pipe and supplies the extracted steam into the containment vessel.

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