JPH09288193A - Boiling water reactor built-in type coolant recirculation system and its operation method - Google Patents

Abstract

(57) [Summary] (Correction) [Problem] Even when the AC bus in the station is out of service or the power is lost, the cooling water recirculation device with a built-in reactor can perform a predetermined rated flow rate or a predetermined flow rate coast down operation. ,
Moreover, the present invention provides a coolant recirculation device with a built-in reactor capable of reducing the number of RIP systems, improving the economic efficiency by reducing the initial investment of power generation equipment and the inspection and maintenance cost, and its operating method. SOLUTION: An IMG 20 is operated as a generator by a signal of an instantaneous power failure or power loss of an in-house AC bus 2 to generate FW2.
1 is converted into AC power, and the control device 14 controls the VVVF 6 to output a DC voltage capable of supplying an AC voltage having a frequency corresponding to the operating speed of the RIP 11; And is supplied to the rectifier output side DC circuit of the VVVF6.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a power source for driving an RIP (boiling water reactor built-in induction motor drive coolant recirculation pump) and a WIM (pump drive submersible induction motor) for cooling a nuclear power plant. A boiling water reactor built-in coolant that prevents damage to the reactor fuel rods and increases the WIM output to reduce the number of pumps installed, in the event of a momentary power failure or loss of power to the AC bus in Recirculation equipment

[0002]

2. Description of the Related Art In boiling water nuclear reactors, a method of controlling the coolant recirculation flow rate in the core of the nuclear reactor is adopted as one means for controlling the output of the nuclear reactor. This will be described with reference to the system configuration diagram of FIG. 20. A part of the output of the nuclear turbine generator 1 is used as the in-house AC bus 2, the in-house transformer 3,
The voltage is input to the input transformer 5 via the circuit breaker 4, and a predetermined voltage is supplied by the input transformer 5 to supply power to VVVF (variable voltage variable frequency power supply device) 6. The VVVF 6 converts the input voltage into a direct current by the built-in rectifier 7 and the smoothing device 8 and then reverse-converts it in the reverse converter 9 to generate an alternating current having a frequency and a voltage specified by a control signal from the control device 14, and an output transformer. Ten
Power is supplied to the WIM 12 via the RIP 11 to change the rotation speed of the RIP 11 to control the coolant recirculation flow rate in the core.

Since the RIP 11 is installed inside a nuclear reactor, the outer diameter of the rotating body cannot be increased due to structural restrictions, and the rotational inertia energy stored therein is small. Therefore, at the time of a momentary power failure or loss of power to the in-house AC bus 2, the rotational speed of the pump rapidly decreases and the core flow rate sharply decreases, as shown in FIG. 21, so that the fuel rods loaded in the core are thermally damaged. May occur. In order to avoid this, as shown in FIG. 20, an MG driven between an in-house transformer 3 and an input transformer 5 by an induction motor having a large rotary inertia energy held by a rotating body.
(Induction motor driven AC generator) 78 is interposed to supply electric power from the bus bar to VVVF6 via MG78, and at the time of momentary power failure or power loss, a rapid decrease in core flow rate is suppressed by this rotary inertia energy, and fuel rod It is designed to prevent thermal damage.

As shown in FIG. 22, a WIM 12 for driving a pump is installed in water under a boiling water reactor pressure vessel 31 in a motor casing nozzle 32 which communicates with reactor water of a nuclear reactor. In order to cool the heat input transferred from the furnace by heat conduction, the copper loss and iron loss of the electric motor, and the heat generated by the mechanical loss, the auxiliary pump 39 built into the thrust plate directly connected to the WIM rotor 36 Of water,
This is an R installed outside via the RIP cooling water pipe 40.
It is circulated to the primary side 42 of the IP cooling heat exchanger 41 and its secondary side
In the seawater cooling heat exchanger 53 circulating through 43, heat is exchanged with the cooling water cooled by the seawater.

Further, a plurality of RIP11s or VVVF6s constituting the boiling water reactor built-in type coolant recirculation device.
If one of them fails, the operating speed of the remaining healthy RIP is increased to ensure the coolant recirculation flow rate that enables the reactor rated output operation. By the way,
The boiling water reactor used in a plant with an electric output of 1340 MWe is equipped with 10 RIP systems,
Even if one RIP system stopped operating, the rotation speed of the remaining 9 RIP systems was increased to 1350.
It is designed to obtain the electric output of MWe.

[0006]

As described above, the RIP
The VVVF that drives the
Although it is highly reliable and has excellent responsiveness, in order to compensate for the sudden drop in flow rate due to the shortage of RIP rotational inertia energy when there is a momentary power failure of the AC bus inside the plant or power loss, MGs with large rotational inertia energy are connected in series. Inserting. This M
G is a large-sized rotating machine and requires many auxiliary equipment such as a bearing lubrication pump, so that it has the drawbacks of low reliability, large installation space, and poor operating efficiency.

The WIM circulates the cooling water from the inside of the WIM to the RIP cooling heat exchanger 41 installed outside by the auxiliary pump 39 incorporated in the thrust plate directly connected to the rotor 36.
Increasing the rotation speed of the IP is convenient for increasing the circulation flow rate of the cooling water, but the electric input of the WIM is also increased accordingly, so
There is a drawback that the required cooling capacity also increases. Further, the cooling water supplied to the RIP cooling heat exchanger 41 is, as shown in FIG. 22, another non-regeneration heat exchanger 80 of the reactor cleaning system having a high operating temperature.
Since it is also shared with the heat sink, the temperature is set to 30 ° C, which is higher than the temperature of the seawater to which the heat is dissipated, and the temperature supplied to the WIM is 35 ° C, which allows for the insulation material used for the winding of the stator 35. The temperature difference from the temperature of 90 ℃ becomes small, and WIM
Has the drawback of limiting the permissible current in the winding and hence the motor output.

In a boiling water reactor equipped with a plurality of cooling water recirculation devices with built-in reactors, in order to prepare for a RIP failure during operation, when one fails, the remaining healthy RIP operating speed is maintained. Since the operating method is increased to enable the reactor rated output operation, the reliability of reactor operation will be improved, but the number of installed cooling water recirculation units with built-in reactors will increase, and during normal operation Since the RIP is operated while suppressing its performance, it has a drawback that the effect of capital investment is reduced.

The present invention, in a boiling water reactor equipped with a cooling water recirculation device with a built-in reactor, suppresses the occurrence of thermal damage to the fuel rods loaded in the core during momentary power failure of the AC bus and loss of power. Therefore, FMES that can compensate for power loss of the busbar without compromising the high reliability of the static type VVVF
W by adopting (flywheel energy storage device) and lowering the cooling water temperature of WIM
Improving IM output, reducing the number of RIPs to obtain the core flow required for reactors, improving the reliability of boiling water reactors, and at the same time improving the capital investment effect An object of the present invention is to provide a water recirculation device and an operating method thereof.

[0010]

SUMMARY OF THE INVENTION The boiling water reactor built-in type coolant recirculation system of the present invention is a VVVF from an in-house AC bus.
Drive power to the RIP via the VVVF
AC power is obtained by reverse conversion from the rectifier output side of INV through INV and supplied to the IMG of FMES, and the FW directly connected to the rotation shaft of this IMG is kept rotating at a predetermined rotation speed. In a power supply device that stores as inertial energy the energy required to continue the operation of the RIP required to suppress thermal damage to the fuel rods loaded in the reactor during an instantaneous power failure or loss of power, an instantaneous power failure of the in-house AC bus or The power loss signal causes the IMG to operate as a generator by the current remaining in the circuit, convert the inertial energy stored in the FW into AC power, and the control device causes the VVVF to generate an AC voltage with a frequency corresponding to the operating speed of the RIP. VVV is converted into DC power through INV controlled so as to output a DC voltage that can be supplied.
RIP by supplying to the rectifier output side DC circuit of F
The main feature is to have a RIP drive power supply device capable of continuing the above operation for a predetermined time. In addition,
The FMES may be replaced with a static SMES.

Further, the operating method of the coolant recirculation apparatus with built-in boiling water reactor of the present invention is as follows:
Drive power is supplied to multiple RIPs via
Supplying power to FMES or SMES from the rectifier output side of VVVF, and continuing the RIP operation necessary to suppress thermal damage to the fuel rods loaded into the reactor during momentary power failure of the AC bus in the plant or loss of power In a power supply device that stores the impetus energy as inertial energy or magnetic field energy, if one RIP fails, the control rods will be operated until the core heat output does not cause thermal damage to the fuel rods loaded in the core. After inserting and lowering the reactor power, repair the power to recover the power, or if repair is not possible, the core without the risk of thermal damage to the fuel rods loaded into the core until the scheduled shutdown of the reactor. The feature is that the control rod is inserted until the heat output is reached, the reactor output is reduced, and the reactor operation is continued.

[0012]

In the invention of claim 1 of the present invention, when a signal of a momentary power failure or a power loss of the in-house AC bus is input to the control device, the IMG driving the FW is stored in the FW. Using the rotating inertia energy as driving energy, it becomes an AC generator and supplies AC power to INV. INV is converted into DC power by inverse conversion to the DC circuit of the VVVF rectifier output side, and the voltage of the DC circuit is set to a predetermined value during an instantaneous power failure. With the DC voltage to be maintained, when the power supply is lost, the voltage of the DC circuit is coordinated with the control procedure incorporated in the VVVF control device, and the VVVF supplies the AC power output to the RIP with the DC voltage that can efficiently supply the power. R to secure core flow rate to prevent thermal damage to fuel rods loaded in the reactor
IP operation continues.

According to a second aspect of the present invention, in the first aspect of the invention, FMES is replaced with SMES (superconducting energy storage device). The SMES is a static type and has no rotating part, and can improve the reliability of the RIP driving power supply device.

According to a third aspect of the present invention, in the RIP driving power supply device, a plurality of RIPs installed in the boiling water reactor.
R to supply the driving power to the reactor and to suppress the thermal damage of the fuel rods loaded in the reactors to the multiple RIPs in the event of a momentary power failure or loss of power of the in-house AC bus.
Energy to keep IP running is stored in FMES, and one VVVF is used during normal operation.
Drives a plurality of RIPs, and operates in the same manner as in the first aspect of the invention when there is a momentary power failure or power loss of the in-house AC bus. In this case, electric power is supplied to the VVVF to increase the energy stored in the FW of the FMES and to secure the core flow rate that prevents the thermal damage of the fuel rods loaded in the reactor by the capacity of the IMG and INV. It is desirable to enhance it so that

According to a fourth aspect of the present invention, a part of the plurality of RIPs installed in the boiling water reactor is driven by the RIP driving power supply device, and the rest is a VV having no FMES or SMES.
It is characterized by being driven by VF. During normal operation, RIP and FM driven by VVVF equipped with FMES
The RIP driven by VVVF which is not equipped with ES supplies the core flow required for reactor operation. In the event of a momentary power failure or loss of power to the in-house AC bus, a VV equipped with FMES
Although it operates similarly to the invention of claim 1 with respect to the RIP driven by the VF, the RIP driven by the VVVF not equipped with the FMES has a small rotational inertia, so that the rotational speed is rapidly reduced in consideration of the fuel. The core flow rate that prevents thermal damage to the rods is calculated in advance, and the power required to secure that flow rate is coordinated with the control procedure incorporated in the VVVF controller equipped with FMES, and VVVF is RIP Power is supplied by a DC voltage that can efficiently supply the AC power output to the. In this case, the core flow rate which increases the energy stored in the FW of the FMES and also prevents the thermal damage to the fuel rods loaded into the reactor is driven by the VVVF without FEMS. It is desirable to increase the power to be reserved so as to be able to supply VVVF, including the rapid reduction in the rotation speed of the RIP, the reduction in the flow rate due to the stoppage, and the compensation for the reverse flow.

The invention of claim 5 is characterized in that the IMG and FW of FMES are housed in a vacuum or depressurized container, and the IMG and FW of FNES are installed inside the depressurized container and attached. By exhausting with an exhaust device and placing in a decompressed atmosphere, windage loss caused by rotation is reduced, and rotational inertia energy is effectively stored. In this case, since the windage loss is reduced by reducing the pressure, it is possible to store the desired rotational inertia energy in a smaller device by rotating the IMG and FW at high speeds.

The invention of claim 6 is characterized in that the cooling heat exchanger of the RIP WIM is supplied with the refrigerant of the refrigerator or the chilled water cooled by the refrigerant, and the winding of the WIM is wound. The heat generated in the iron core and the heat transferred from the high-temperature reactor vessel by heat conduction are cooled by generating water flow around the stator and rotor by the auxiliary pump incorporated in the thrust plate under the WIM, and the temperature is increased. The water is sent to the RIP cooling heat exchanger installed outside, where it is heat-exchanged with the refrigerating machine refrigerant or cold water circulated from the refrigerating machine, and the cooled water is returned to the WIM. When cold water having a low temperature near 0 ° C. is desired as the water to be returned to the WIM, water is frozen as a cooling fluid for the RIP cooling heat exchanger, so a refrigerant having a low freezing temperature is used.

The invention of claim 7 is characterized in that the cooling heat exchanger of the RIM WIM is supplied with a refrigerant or cold water cooled by heat exchange with the cold heat medium stored in the regenerator. Therefore, the refrigerator in claim 6 is replaced by a regenerator, and the same operation is performed. The cold stored in the regenerator and consumed by the cooling of the RIP cooling heat exchanger is supplied by the attached regenerator refrigerator. The refrigerator for the regenerator may be operated continuously in proportion to the amount of cooling required for the RIP cooling heat exchanger, but as the capacity for storing the cold required for cooling the regenerator for a certain period, the cold consumed in a certain cycle is used. It may be an intermittent operation for supplying the regenerator to the regenerator.

The invention of claim 8 is characterized in that cold water cooled by a dedicated seawater cooling heat exchanger or an air cooling heat exchanger is supplied to the cooling heat exchanger of the RIP WIM. R is used as a cold heat source by using seawater or the atmosphere cooled through a seawater cooling heat exchanger or an air cooling heat exchanger.
Supply cooling water to the IP cooling heat exchanger.

In this case, RIP may occur due to day and night or seasonal fluctuations.
When the cooling water of the desired temperature cannot be supplied to the cooling heat exchanger, it is desired by the refrigerator or the regenerator connected in parallel with the seawater cooling heat exchanger or the air cooling heat exchanger by operating the switching control valve. To the RIP cooling heat exchanger 41 by using the seawater cooling heat exchanger or the air cooling heat exchanger together with the refrigerator or the regenerator with the switching control valve at an intermediate opening degree. You may make it cool to the temperature of.

According to a ninth aspect of the present invention, the cold water for cooling the WIM is W.
It is characterized in that it is circulated by a pump directly connected to the IM, and the cooling water that cools the WIM is circulated by an auxiliary pump incorporated in a thrust plate directly connected to the rotation shaft of the WIM to The heat generated and the heat transferred from the high temperature reactor vessel by heat conduction are sent to the RIP cooling heat exchanger installed outside, where the refrigerator, the regenerator,
Heat can be exchanged with the refrigerant or cold water from the seawater cooling heat exchanger or the air cooling heat exchanger.

The invention of claim 10 is characterized in that the cold water for WIM cooling is circulated by a cooling water circulation pump installed outside, and the cooling water is pumped by operating the cooling water circulation pump installed outside the RIP. WIM to RIP
It can be circulated to a cooling heat exchanger where it can be heat exchanged with refrigerant or cold water from a refrigerator, regenerator, seawater cooling heat exchanger or air cooling heat exchanger.

According to the eleventh aspect of the present invention, the cooling water circulation pumps are connected in parallel via a cooling water pump switching valve in preparation for a failure of the cooling water circulation pump. Is circulated from the WIM to the RIP cooling heat exchanger, and at the time of failure, the cooling water pump switching valve is operated to maintain the cooling water circulation.

According to a twelfth aspect of the present invention, the circulating flow rate of the cooling water circulation pump is controlled according to the RIP rotation speed or the drive current, drive voltage or drive power of the WIM. Most of the heat generated is WIM
Optimum cooling water flow rate that suppresses temperature changes of the WIM winding and the iron core by inputting signals of driving current or driving voltage, rotation speed and cooling water temperature into the cooling water flow rate control device in view of being proportional to the driving power of Is calculated using a functional relationship in which the driving power is approximately proportional to the cube of the RIP rotation speed, and a control signal is transmitted to the flow rate adjusting valve and the cooling water circulation pump.
It suppresses the temperature change of the WIM winding and the iron core with respect to the change of the operating condition.

The thirteenth aspect of the present invention is characterized in that the temperature of the cold water for cooling the WIM is controlled according to the RIP rotation speed or the drive current, drive voltage or drive power of the WIM. The circulating flow rate of the cooling water by the auxiliary pump directly connected to the WIM is almost proportional to the RIP rotation speed, but the driving power of the WIM increases in proportion to the cube of the RIP rotation speed. Increases in proportion to the square of the rotation speed. The drive current, drive voltage or rotation speed of WIM and the signal of the cooling water temperature are input to the circulating refrigerant control device to control the temperature and circulating flow rate of the refrigerant supplied to the RIP cooling heat exchanger, thereby controlling the RIP cooling heat exchanger. By controlling the temperature difference between the primary side and the secondary side, it is possible to suppress an increase in the cooling water temperature of the WIM.

The invention according to claim 16 is the number of RIPs,
It is characterized in that the core flow rate for obtaining the rated output at the end of the operation cycle of the boiling water reactor is set to a maximum integer that does not exceed the quotient obtained by dividing by the RIP rated maximum flow rate. In the present invention, the rotational speed of the RIP is increased to increase the rated flow rate to reduce the number of RIPs equipped in the boiling water reactor, but in this case, the drive power of the WIM is also increased and the WIM winding or Since the amount of heat generated by the iron core increases, the core is cooled below the allowable temperature of the insulating coating material used for the WIM winding. Also, RI
When reducing the number of P, the decrease in the core flow rate due to the failure of the RIP and its driving power source has a large effect on the thermal damage to the fuel rods loaded in the core. Therefore, the reliability of the power system is improved as described above. Improve.

According to a fifteenth aspect of the present invention, the V
Driving power is supplied to a plurality of RIPs via the VVF, and power is supplied from the rectifier output side of the VVVF to the FMES or SMES. In a power supply device that stores, as inertial energy or magnetic field energy, energy for continuing RIP operation required to suppress thermal damage to rods, a fuel rod loaded in the core when one RIP fails Control rods are inserted until the core heat output does not cause thermal damage to the reactor and the reactor output is reduced, and then repair is performed to recover the output, or if the reactor cannot be repaired, when the reactor is planned to stop. Insert the control rod until the core heat output does not cause thermal damage to the fuel rods loaded in the core, lower the reactor output, and continue the reactor operation. It is characterized in. RI
In the event of a P system failure, a slight decrease in operating rate is tolerated, and thermal damage to the fuel rods loaded in the reactor is suppressed by R
Increase the initial equipment investment by increasing the number of installed RIP systems and providing redundancy to reduce the reactor output to a value commensurate with the core flow reduction due to an IP system failure and to prevent damage due to a decrease in operating rate. Can be avoided.

The cumulative operation record of the cooling water recirculation system with a built-in reactor operating in Europe exceeds 10 million hours / unit, and there is almost no failure experience that requires repair by opening the reactor vessel. , Failure rate λ at which such failures occur
Is estimated to be 10 ^-6 h ^-1 or less. According to reliability engineering,
The reliability R after the t-hour operation of the power generation equipment configured by the RIP system N having the finite failure rate λ that constitutes the boiling water reactor power generation equipment is expressed as R = exp (−λ · N · t) Therefore, if the number of RIP system components is reduced, the reliability of the power generation equipment is improved. Assuming that a periodic inspection is performed every 55 days, the mean time to failure (MTBF) for 10 RIP systems is 13.4 years, 8 years.
In the case of a stand, it will improve to 16.8 years. If one fault is tolerated, the reliability of the generator will be R '= exp (-λ ・ N ・ t) + N ・ exp {-λ ・
(N-1) · t} can be improved. MTBF can be improved to 28.4 years by allowing 1 failure in the case of 10 units, but one or two times of failure is forced to open the reactor vessel within 40 years of the design life of the power generation facility. Therefore, there is not much difference from the encounter frequency of 2-3 times when the failure of one of the eight is not allowed. Further, for the occurrence of a failure that can be repaired while continuing the operation of the nuclear reactor, such as a failure of the power supply system, the frequency of failure occurrence can be reduced by applying the invention described in claims 1 to 5. it can. As a result, RI of power generation equipment
By reducing the initial investment amount and maintenance and inspection costs by reducing the number of P systems, and improving the reliability of the drive power supply system, the operating rate of power generation equipment equipped with a cooling water recirculation device with a built-in reactor can be increased. The economical efficiency of the power generation equipment can be improved.

According to a sixteenth aspect of the present invention, in the power supply device, the cold water cooled by the dedicated seawater cooling heat exchanger or the air cooling heat exchanger is supplied to the cooling heat exchanger of the RIP WIM. If the cold water temperature obtained by the cooling or air cooling heat exchanger is sufficiently low and the cold water at the predetermined temperature required for WIM cooling can be supplied via the WIM cooling heat exchanger, activate the seawater cooling or air cooling heat exchanger. When seawater or the ambient temperature is too high to supply cold water of a predetermined temperature necessary for WIM cooling, the seawater cooling or air cooling heat exchanger is not operated, and the refrigerant of the refrigerator or the cold water cooled by the refrigerant or the regenerator It is characterized in that the refrigerant or cold water cooled by heat exchange with the cold heat medium stored in the power generation facility is supplied. W from the operating conditions of the RIP system
The cooling conditions of the IM are determined, the cooling temperature of the seawater cooling air exchanger or the air cooling heat exchanger is calculated from the fluctuation tendency of the seawater or atmospheric temperature, and the cooling temperature is predicted to exceed the temperature desired for WIM cooling. In this case, by operating the switching control valve to switch to cooling by the refrigerator or the regenerator, cold water at a desired temperature can be supplied to the RIP cooling heat exchanger.

It should be noted that the WIM cooling conditions are determined from the operating conditions of the RIP system according to the power generation plan imposed on the power generation equipment, and the cooling temperature of the seawater cooling heat exchanger or the air cooling heat exchanger is determined from the fluctuation tendency of the seawater or atmospheric temperature. When the cooling temperature is predicted to exceed the desired temperature for WIM cooling, the chilled water at the desired temperature is RIP-cooled by operating the switching control valve together with the cooling by the refrigerator or the regenerator. It can also be supplied to a heat exchanger. Further, as a means for increasing the output of the WIM of the RIP system, the temperature of the cooling water supplied to the WIM is lowered or the flow rate of the cooling water is increased to form the WI which becomes the heat generating portion.
It is also possible to increase the temperature difference between the M stator surface and the rotor surface or the heat transfer coefficient to suppress the temperature rise of the WIM winding so that the temperature is not more than the allowable temperature of the insulating material used for the winding.

[0031]

Next, an embodiment of the present invention will be described with reference to the drawings.

In the first embodiment, as shown in FIG. 1, part of the output of the nuclear turbine generator 1 is input to the input transformer 5 via the in-house AC bus 2, the in-house transformer 3 and the circuit breaker 4. ,
The input transformer 5 converts the voltage to a predetermined voltage to supply power to VVVF 6, and the built-in rectifier 7 and smoother 8 convert the voltage to direct current.
The AC voltage frequency adjuster 15 receives the control signal F from the control device 14 and sends a control signal G for controlling the RIP 11 to a predetermined rotation speed to the inverse converter 9. As a result, the inverse converter 9 supplies power to the WIM 12 via the output transformer 10 as an alternating current having a frequency and voltage specified by the control signal G.

A part of the direct current of the rectifier 7 is fed to the FMES 17, and the INV (inverter device) 19 that constitutes the FMES 19
Is converted into DC / AC voltage by the control signal P of the control device 14 and AC of the frequency / voltage specified by the control signal Q transmitted from the frequency adjuster 16, drives the IMG 20, and stores a predetermined rotational inertia energy in the FW 21. To do. Further, the control device 14 monitors the AC voltage signal V supplied to the VVVF 6 and detects the rotational speed signal R of the RIP 11 by the momentary power failure or the AC bus power loss signal S, and the RIP 11 is, for example, as illustrated in FIG. , The new control signals P, Q, F and G are transmitted to the DC / AC voltage and frequency regulator 16 and the AC voltage regulator 15 so that the predetermined number of revolutions is achieved, and the energy stored in the FW is used. AC power generation with IMG20, INV19
And RIP11 via the inverse converter 9 of VVVF6. The number of revolutions designated in advance is from time Td to T in FIG.
It may be constant as indicated by the predetermined rotation speed of a, or may be changed in consideration of the fuel rod surface temperature. In this case, the control start time Td is the momentary power failure or power loss detected at time To. , RIP11 rotational speed is detected, and the delay time required to determine the control signal is restricted.

The FMES 17 is electrically connected in parallel with the RIP 11 and can be operated at a rotation speed independent of the rotation speed of the RIP 11. Since the stored energy of FW21 is proportional to the square of the rotation speed, it is possible to reduce the size of the device by operating it at a high rotation speed. In addition, FMES17
As shown in FIG. 23, is an electric power that can maintain a predetermined rotation speed for a time (Ta-Td) required to prevent thermal damage to the fuel rods loaded in the core during momentary power failure or loss of AC power supply. As long as it has the ability to supply power, the IMG 20 may be miniaturized as a short-time rating, for example, 30 minutes rating, if the IMG 20 has a rated output that maintains the high speed rotation of the FW 21 as an induction motor. .

By connecting FMES17 in parallel,
Since the failure of FMES does not immediately affect the operation of RIP11, even if there is a momentary power failure or power loss of the AC bus, there is no thermal damage to the fuel rods. Various operations are possible.

In the second embodiment, as shown in FIG. 2, one VVVF6 drives a plurality of RIP11.
The energy stored in ES17 is given to a plurality of RIP11, and as illustrated in FIG. 23, a predetermined time (Ta) required to prevent thermal damage to the fuel rods loaded in the core during momentary power failure or loss of AC power source (Ta -Td) has been enhanced so that power can be supplied to maintain RIP11 at a predetermined rotation speed. As a result, the same effect as that of the first embodiment can be obtained. It is also possible to drive the entire RIP11 installed in the reactor with a VVVF6 equipped with one FMES17,
In order to improve the safety of reactor operation in the event of a failure of F or the failure of the power transmission circuit consisting of the on-site transformer 3, circuit breaker 4, or conductors, as shown in FIG. It is desirable to divide the RIP 11 connected to the device 3 into a plurality of sets and to equip each set VVVF 6 with the FMES 17. Further, by consolidating the FMES 17 which is a dynamic rotating machine, inspection and maintenance are facilitated, and the reliability of the FMES is improved.

In the third embodiment, as shown in FIG. 4, one of the RIPs 11 connected to the on-site transformer 3 is replaced by the FMES17.
Driven by VVVF6 which is not equipped, and the remaining RIP is FM
It is driven by a VVVF6 equipped with an ES17, and the energy stored in the FMES17 is a predetermined rotational speed determined in consideration of the rotational speed reduction of the RIP11 not equipped with the FMES17 and the flow reduction and backflow due to the stop, Figure 2
As illustrated in Fig. 3, the amount of time during which the operation can be continued from time Td to time Tb is set, and a predetermined time (Tb required to prevent thermal damage to the fuel rod loaded in the core during momentary power failure or loss of AC power supply). Only −T d) is supplied. In this case, the same effect as in the first embodiment can be obtained.

In the fourth embodiment, as shown in FIG. 5, among the RIPs 11 connected to the on-site transformer 3, the number of RIPs driven by the VVVF6 equipped with the FMES17 is one or two, and the VVVF6 not equipped with the FMES17. Driven by RI
This is a system configuration in which the number of P units is one. In this case also, the energy stored in FMES is
23. The fuel rods loaded in the core at momentary power failure or AC power loss are set so that the operation illustrated in FIG. The power is supplied for a predetermined time (Tb-Td) required to prevent thermal damage to the battery. Also in this case, the same effect as the third embodiment can be obtained.

In the fifth embodiment, as shown in FIG. 6, among the RIPs 11 connected to the in-house transformer 3, the number of RIPs driven by the VVVF6 equipped with the FMES17 is one or two, and the VVVF6 not equipped with the FMES17. Driven by RI
The system configuration has two or one P units. Also in this case, the energy stored in FMES is
The amount that can be continued from time Td to time Tb illustrated in FIG.
Specified time (Tb-Td) required to prevent thermal damage to the fuel rods loaded in the core during momentary power failure or loss of AC power
By supplying power only, the same effect as in the third or fourth embodiment can be obtained.

In the sixth embodiment, as shown in FIG.
The IMG20 and the FW21 of the rotating part constituting the S are housed in the decompression container 22, and the exhaust device 23 exhausts the atmosphere in the container 22 to a decompressed atmosphere to reduce the windage loss due to the rotation of the IMG20 and the FW21, thereby reducing the FMES. It is intended to reduce the energy loss during operation of the reactor due to the installation. In this case, the rotation speed of the FW 21 is detected by the rotation speed meter 26, and the transmission line for transmitting the electric signal converted by the rotation speed converter 27 and the power line connected to the IMG 20 are connected to the penetration 28 that hermetically penetrates the decompression container 22. , 29 to be connected to the outside to keep the inside of the decompression container 22 in a decompressed state. The pressure in the decompression container 22 is measured by the pressure converter 25, and the operation of the exhaust device 23 is controlled. If the reduced pressure container 22 has a high ability to hold the reduced pressure state, the isolation valve 24 may be closed to isolate the exhaust device 23. Further, during normal operation, the IMG 20 needs to be kept at a predetermined rotation speed in order to store the rotational inertia energy of the FW 21, and heat is generated due to its driving power.
It is desirable to keep 20 at a given temperature. The sixth embodiment can be used in the first to fifth embodiments.

In the seventh embodiment, as shown in FIG.
The configuration of the cooling system of the RIP is such that the rotating part constituted by inserting the RIP impeller 33 into the rotor 36 of the WIM having the auxiliary pump 39 incorporated in the thrust plate at the lower part is disposed at the lower part of the reactor vessel 31. It is supported by two radial bearings 37 fixed to the WIM housing 34 in the motor casing nozzle 32 attached to and two sets of upper and lower thrust bearings 38.
Similarly, a WIM stator 35 fixed to the housing 34 is driven by applying a multi-phase alternating current. An auxiliary pump (impeller) 39 incorporated in the thrust plate pressurizes the cooling water by the action of centrifugal force to pass through a gap between the thrust bearing 38, the lower journal bearing 37 and the rotating portion, and a bypass flow path (not shown). ,
It is introduced into the periphery of the stator 35 to cool the heat generated by the copper loss and iron loss of the stator 35 and the copper loss and iron loss of the rotor 36 of the WIM, and further the gap of the upper journal bearing 37 and the bypass passage (not shown). Through the RIP cooling water pipe 40 welded to the motor casing nozzle 32 above the housing 34
To be discharged from

The cooling water discharged from the RIP cooling water pipe 40 by cooling the WIM 12 and raising the temperature is cooled by the RIP cooling heat exchanger 41.
R that is cooled by the refrigerant that flows into the primary side 42 of the motor 42 and is pressure-fed from the refrigerator 45 connected to the secondary side 43 through the refrigerant pipe 44, and is welded to the lower portion of the motor casing nozzle 32.
It flows through the IP cooling water pipe 40 and returns to the suction side of the auxiliary pump 39 incorporated in the thrust plate. The refrigerant flowing through the refrigerant pipe 44 to the secondary side 43 of the RIP cooling heat exchanger 41 may directly flow the refrigerant of the refrigerator 45, or instead of the refrigerant, the refrigerant 45 and the heat of the water can be used. A cold water is made by attaching an exchanger, and this cold water is subjected to RIP cooling heat exchanger by a cold water circulation pump 46.
It may flow to the secondary side 43 of 41. One refrigerator 45 may cool a plurality of RIP cooling heat exchangers 41, or the refrigerator 45 may be shared with, for example, a building air-conditioning refrigerator. Further, the RIP cooling heat exchanger 41 that cools the cooling water of a plurality of RIPs has a common secondary side, and one refrigerator has a plurality of RIPs.
The IP may be cooled.

In the eighth embodiment, as shown in FIG. 9, WIM12
In the same manner as in the seventh embodiment, in order to cool the cooling water circulating in the primary side 42 of the RIP cooling heat exchanger 41, the refrigerant circulating in the secondary side 43 is Cool with a heat exchanger built in or attached to the vessel 47. The refrigerant is circulated from the refrigerator 48 for the regenerator to the regenerator 47, and the RIP
The cold consumed in the cooling in the cooling heat exchanger 41 is replenished. The cold storage capacity of the regenerator 47 may be, for example, an amount required for operating the RIP for one day, and the refrigerator 48 for regenerator for cold replenishment may be operated at night with electric power at midnight. The RIP cooling heat exchanger 41 and the regenerator 47 may be combined and integrated, and a plurality of RIP cooling units may be combined into one regenerator 47.
May be done in. Further, the regenerator refrigerator 48 may be shared with, for example, a building air conditioning refrigerator.

The ninth and tenth embodiments relate to the configuration of the cooling system of the WIM 12 as shown in FIGS. 10 and 11. In these embodiments, as in the eighth embodiment,
In order to cool the cooling water circulating in the RIP cooling heat exchanger primary side 42, the cooling water supplied to the RIP cooling heat exchanger secondary side 43 is cooled by the seawater cooling heat exchanger 53 or the air cooling heat exchanger 59. I am trying to get it. The cold water obtained by the seawater cooling heat exchanger 53 or the air cooling heat exchanger 59 is a plurality of RIPs.
It may be supplied to the cooling heat exchanger 41. It is possible to integrate the RIP cooling heat exchanger 43 and the seawater cooling heat exchanger 53 or the air cooling heat exchanger 59 to simplify the system, but the cooling water circulating through the primary side 42 of the RIP cooling heat exchanger. Is in communication with the recirculating cooling water that cools the core in the reactor, so if the heat transfer surface is damaged, radioactivity may leak to seawater or the atmosphere, which is not preferable. Rather, the pressure of the cooling water circulation system interposed between the RIP cooling heat exchanger 41 and the seawater cooling heat exchanger 53 or the air cooling heat exchanger 59 is adjusted to prevent radioactive leakage to the circulation of seawater or the atmosphere. Raise the pressure higher than the furnace pressure and detect the damage on the heat transfer surface of the heat exchanger due to the pressure drop, and stop the operation of the corresponding RIP
Isolate the cooling heat exchanger 41, take measures to prevent damage spread,
It is better to improve safety. For isolation of the RIP cooling heat exchanger 41, an isolation valve may be installed in advance in the cold water pipe 51, and freeze closing can be performed with liquid nitrogen or dry ice.

In the eleventh embodiment, as shown in FIG.
Regarding the configuration of the M12 cooling system. In the ninth embodiment, RI
P cooling heat exchanger A method of cooling the cooling water supplied to the RIP cooling heat exchanger secondary side 43 for cooling the cooling water circulating in the primary side 42 by the seawater cooling heat exchanger 53 or the air cooling heat exchanger 59. showed that. However, in case the temperature of the cold water supplied to the RIP cooling heat exchanger 41 cannot satisfy the cooling specifications of WIM12 due to the seasonal fluctuation of the seawater temperature or the atmospheric temperature,
A seawater cooling heat exchanger 53 or an air cooling heat exchanger 59, and
The refrigerator 45 or the regenerator 47 described in the embodiment and the eighth embodiment
Is more preferably connected in parallel via the switching control valve 63, and the cooling circuit is switched when the seawater temperature or the atmospheric temperature rises to supply cold water of a predetermined temperature to the RIP cooling heat exchanger 41. In this case, the cold water obtained by the seawater cooling heat exchanger 53 or the air cooling heat exchanger 59 and the refrigerator 45 described above are used.
Alternatively, the cold water obtained in the regenerator 47 is mixed by operating the switching control valve 63, and the cold water having a predetermined temperature is supplied to the RIP cooling heat exchanger 41. In addition, the RIP cooling heat exchanger secondary side 43 is shared, and the RIP cooling heat exchanger primary side of a plurality of RIPs is used.
42 may be independently cooled.

In the twelfth embodiment, as shown in FIG.
Regarding the configuration of the IM12 cooling system. In the seventh to tenth embodiments, the WIM cooling system has an auxiliary pump 39 incorporated in the thrust plate as in the conventional example shown in FIG.
However, in the twelfth embodiment, the auxiliary pump directly connected to the WIM 12 is removed, and instead the cooling water circulation pump 66 is installed and supplied from the RIP cooling heat exchanger primary side 42. The cooling water to be supplied is supplied from the lower part of the motor casing nozzle 32 to the thrust plate 65 below the WIM.
It is designed to be pumped to the space below. The cooling water pumped to the lower part of the WIM flows into the periphery of the WIM stator 35 through the gap between the thrust bearing 38 and the lower journal bearing 37 and the rotating part and the bypass flow path (not shown), and
The heat generated by the copper loss and iron loss of the IM stator 35 and the copper loss and iron loss of the WIM rotor 36 are cooled and passed through the gap of the upper journal bearing and the bypass passage (not shown), and the motor casing above the WIM housing 34. -It is discharged from the RIP cooling water pipe 40 welded to the nozzle 32. The cooling water thus discharged flows into the RIP cooling heat exchanger 41, is cooled again, and is returned to the suction side of the cooling water circulation pump 66.
In the case of this embodiment, a plurality of WIMs, one RIP cooling heat exchanger 41 and cooling water circulation pump 66 may be combined,
Alternatively, the RIP cooling heat exchanger secondary side 43 is commonly used, and RI
The P cooling heat exchanger primary side 42 and the cooling water circulation pump 66 may be independent for each WIM. The seventh to eleventh embodiments can be applied to the cooling of the secondary side 43 of the RIP cooling heat exchanger. Also, a cooling water circulation pump
66 may be installed on the discharge side of the RIP cooling water pipe 40 welded to the upper part of the motor casing nozzle 32 of the WIM housing 34.

In the thirteenth embodiment, as shown in FIG.
The present invention relates to a method of installing a plurality of cooling water circulation pumps 66 outside P. That is, a plurality of cooling water circulation pumps 66 are connected in parallel via a cooling water pump switching valve 67, and the pump switching valves 67 before and after one of the pumps are closed to stand by. In this case, when the cooling water circulation pump 66 in operation fails, the standby cooling water circulation pump 66 is activated and the cooling water is circulated by operating the pump switching valve 67, and at the same time the switching valve 67 before and after the failed pump is closed. It can be isolated and repaired.

In the fourteenth embodiment, as shown in FIG.
The present invention relates to a method for controlling the cooling water flow rate and temperature of the M cooling system. In this embodiment, a flow rate adjusting valve 70 is provided on the discharge side of the external cooling water circulation pump 66 shown in the twelfth and thirteenth embodiments, and the cooling water flow rate control device 71 is provided with the RIP rotation speeds N and WIM. Driving current I and the RIP outlet temperature T of the cooling water are input, and the cooling water flow rate is increased / decreased and the flow rate adjusting valve is adjusted so that the cooling conditions defined by the WIM specifications are satisfied. The opening of 70 is adjusted to control. In this case, the operating conditions of the refrigerator 45 and the chilled water circulation pump 46 are operated by the signal from the cooling water flow rate control device 71,
The operating temperature and flow rate of the RIP cooling heat exchanger secondary side 43 may be adjusted.

In the fifteenth embodiment, as shown in FIG.
The present invention relates to a method for controlling the cooling water temperature of the cooling system of P's WIM12. Auxiliary pump incorporated in WIM thrust plate
In the system in which the cooling water for the WIM is circulated by 39, the circulation flow rate of the cooling water is determined by the rotation speed of the WIM, and it is impossible to increase the flow rate beyond that and enhance the ability to cool the WIM. Therefore, in this embodiment, signals of the rotational speed N of the RIP, the drive current I of the WIM, and the RIP inlet and outlet temperatures T1 and T2 of the cooling water are input to the circulating refrigerant control device 73, and are determined by the WIM specifications. The operation signals C1 and C2 are transmitted to the chilled water circulation pump 46 and the regenerator refrigerator 48 so as to satisfy the cooling conditions, and the operating conditions of the RIP cooling heat exchanger secondary side 43 are controlled.

The sixteenth embodiment is a constitutional example of a cooling water recirculation system for a boiling water reactor power generation facility equipped with eight RIP11s as shown in FIG. By the way, the rated speed is 14
10 RIP11 with 00 rpm and rated flow of 2.14 m ³ / s
In a boiling water reactor with an electric output of 1350 MWe equipped with two units, even if one RIP fails and stops, the remaining nine RIPs are accelerated to run the heat of the fuel rods loaded in the core. It is designed to secure the core flow rate that maintains the general soundness. In this case, the number of RIP11 can be reduced by 2 to form 8 units, and if the RIP speed is increased to 125%, the core flow rate can be made equal to that of 10 units.
It is possible to satisfy the nuclear heat design conditions of the core to obtain the electric output of 1350 MWe. In this case, the drive power of the WIM increases and the heat generation amount of the winding of the WIN and the iron core also increases due to the increase in the rotation speed of the RIP. However, according to the inventions described in claims 6 to 13, the cooling of the RIP is performed. Since the water temperature can be lowered from 35 ° C. to about 23 ° C., the insulating material used for the WIM winding can be cooled to the allowable temperature of 90 ° C. or less.

According to the knowledge of reliability engineering, if the number of RIPs equipped in a boiling water reactor is reduced from 10 to 8, the probability of failure of the RIP decreases, and the reliability of the boiling water reactor is reduced. Will improve. Furthermore, by driving with the power supply device described in claims 1 to 5, the frequency of RIP stoppage due to a power supply failure is also reduced, and the reliability of the boiling water reactor is improved. However, although the reliability of the boiling water reactor is improved, the failure rate of the RIP or VVVF has a non-zero finite value, so the failure of the RIP or VVVF cannot be denied. In a boiling water reactor equipped with eight RIPs,
When the RIP or VVVF fails, the control rod is inserted up to the reactor output to prevent thermal damage to the fuel rod loaded in the core, and the reactor output is lowered to operate.

In a boiling water reactor equipped with eight RIPs, the fissionable material in the fuel rods decreases at the end of the operating cycle and the excess reactivity decreases. It is necessary to increase the recirculation flow rate and reduce the void fraction to maintain core power. If one RIP or VVVF fails at such a time, the cooling water recirculation flow rate of the core cannot be secured, and the core output will decrease. Therefore, fuel replacement and periodic inspection are advanced, and the failed RIP
Repair or replace.

The seventeenth embodiment is shown in FIG. Similar to the sixteenth embodiment, this embodiment is a cooling water recirculation device for a boiling water reactor equipped with eight RIP11, and uses SMES75 as a power source for driving the RIP. Since the SMES is a stationary device without a rotating part, the reliability of the power supply can be improved. The operation at the time of RIP or VVVF failure may be the same as in the sixteenth embodiment. Although the case where the number of RIPs is 8 has been described as an example, one R in the boiling water reactor configured by the number of RIPs according to claim 14.
The operation support when the IP is stopped is the same as the case of 8 units.

In the eighteenth embodiment, as shown in FIG.
Regarding the limiting condition of the output of M. Since the flow rate of the pump is proportional to the rotation speed and the pump driving power is proportional to the cube of the rotation speed, V
The drive current of the WIM driven by VVF increases substantially in proportion to the square of the rotation speed, although there is mechanical loss such as friction that does not depend on the rotation speed. When the current increases, heat generation due to copper loss and iron loss increases and the temperature of the winding rises. Therefore, WIM
In the above, cooling is required to keep the temperature below the allowable temperature of the insulating material used for the winding. The allowable current Ic that balances the cooling capacity with the cooling capacity is required. Further, the rotational speed upper limit Nc corresponding to the allowable current Ic is determined from the relationship between the pump rotational speed and the required current.

If the motor is operated at a speed higher than this speed, the insulation temperature of the insulating material used for the winding will be exceeded and insulation deterioration will occur. Therefore, it is necessary to operate the motor at a rotation speed upper limit Nc or less. As shown in FIG. 19, the cooling water flow rate Qc is set to Qx.
If the cooling water temperature Tc is decreased to Ty or the cooling water temperature Tc is decreased to Ty, the allowable current increases to Ix and Iy, so that the operating speed may be increased to Nx and Ny. If Qy and Tx are combined, the allowable current further increases to Iz, so that the operation can be performed with the rotational speed increased to Nz.

The problem to be solved by the present invention is to improve the economical efficiency of a boiling water reactor equipped with a cooling water recirculation device with a built-in reactor, and the number of RIPs constituting the cooling water recirculation device with a built-in reactor. Reduction is the means. In order to reduce the number of units, it is necessary to increase the RIP diameter or increase the number of rotations to increase the flow rate. In either case, WIM
There is no choice but to increase or decrease the output of. In this case, in order to suppress an excessive temperature rise of the WIM winding, the method according to claim 6 to claim 13.
The insulating material used for the winding of the WIM may be cooled to the allowable temperature or lower by enhancing the cooling according to the invention.

[0057]

As described above, according to the present invention, even when the internal AC bus that is the normal driving power source for the cooling water recirculation apparatus with built-in reactor has a power failure or a momentary power failure, the built-in reactor type The cooling water recirculation device can be operated at a specified rated flow rate or a specified flow rate coast down operation, the number of RIP systems that make up the cooling water recirculation device with a built-in reactor can be reduced, and initial investment and inspection and maintenance costs for power generation equipment can be reduced. It is possible to improve economy by reducing As a result, the safety, reliability, operability and maintainability of the boiling water power generation equipment equipped with a cooling water circulation device with a built-in boiling reactor will be greatly improved, and the equipment layout inside the reactor containment building will be reduced by reducing the RIP system. This makes it easier to reduce the construction period and improves the construction quality.

[Brief description of drawings]

FIG. 1 is a configuration diagram of a driving power supply system of a cooling water recirculation device with built-in nuclear reactor according to a first embodiment of the present invention.

FIG. 2 is a drive power system configuration diagram of a cooling water recirculation device with built-in nuclear reactor according to a second embodiment of the present invention.

FIG. 3 is a drive power system configuration diagram of a cooling water recirculation device with built-in reactor according to a second embodiment of the present invention.

FIG. 4 is a drive power system configuration diagram of a cooling water recirculation device with built-in nuclear reactor according to a third embodiment of the present invention.

FIG. 5 is a drive power system configuration diagram of a cooling water recirculation device with built-in nuclear reactor according to a fourth embodiment of the present invention.

FIG. 6 is a drive power system configuration diagram of a cooling water recirculation device with built-in reactor according to a fifth embodiment of the present invention.

FIG. 7 is a configuration diagram of an FMES housed in a decompression container of a cooling water recirculation device with built-in nuclear reactor according to a sixth embodiment of the present invention.

FIG. 8 is a configuration diagram of a cooling system of the RIP used in the cooling water recirculation device with built-in reactor according to the seventh embodiment of the present invention.

FIG. 9 is a configuration diagram of a cooling system of the RIP used in the cooling water recirculation device with built-in reactor according to the eighth embodiment of the present invention.

FIG. 10 is a configuration diagram of a cooling system of the RIP used in the cooling water recirculation device with built-in reactor according to the ninth embodiment of the present invention.

FIG. 11 is a configuration diagram of a cooling system of the RIP used in the cooling water recirculation device with built-in reactor according to the ninth embodiment of the present invention.

FIG. 12 is a configuration diagram of a cooling system of the RIP used in the cooling water recirculation apparatus with built-in reactor according to the eleventh embodiment of the present invention.

FIG. 13 is a configuration diagram of the cooling system of the RIP used in the cooling water recirculation apparatus with built-in reactor according to the twelfth embodiment of the present invention.

FIG. 14 is a configuration diagram of a cooling system of the RIP used in the cooling water recirculation device with built-in reactor according to the thirteenth embodiment of the present invention.

FIG. 15 is a configuration diagram of the cooling system of the RIP used in the cooling water recirculation device with built-in reactor according to the fourteenth embodiment of the present invention.

FIG. 16 is a configuration diagram of a cooling system of the RIP used in the cooling water recirculation device with built-in reactor according to the fifteenth embodiment of the present invention.

FIG. 17 is a drive power system configuration diagram of a cooling water recirculation device with built-in reactor according to a sixteenth embodiment of the present invention.

FIG. 18 is a drive power system configuration diagram of a cooling water recirculation device with built-in reactor according to a seventeenth embodiment of the present invention.

FIG. 19 is a current characteristic diagram of the RIP WIM used in the cooling water recirculation apparatus with built-in reactor according to the eighteenth embodiment of the present invention.

FIG. 20 is a drive power system configuration diagram of a conventional cooling water recirculation device with built-in nuclear reactor.

FIG. 21 is a coast down characteristic diagram of the RIP used in the conventional cooling water recirculation device with built-in nuclear reactor.

FIG. 22 is a cooling system configuration diagram of a RIP used in a conventional reactor-embedded cooling water recirculation device.

FIG. 23 is a coastdown characteristic diagram of the RIP used in the cooling water recirculation device with built-in nuclear reactor according to the present invention.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 ... Nuclear turbine generator, 2 ... In-station AC bus, 3 ... In-station transformer, 4 ... Breaker, 5 ... Input transformer, 6 ... Variable voltage variable frequency power supply (VVVF), 7 ... Rectifier, 8 ... Smoother , 9 ... Inverter, 10 ... Output transformer, 11 ... Reactor built-in induction motor driven coolant recirculation pump (RIP),
12 ... Submersible induction motor (WIM) for driving pump, 13
... Pump, 14 ... Control device, 15 ... AC voltage frequency regulator, 16 ... DC / AC voltage and frequency regulator, 17 ...
Flywheel energy storage device (FMES), 18
… Condenser, 19 ... Inverter device (INV), 20 ...
Induction motor / generator (IMG), 21 ... Flywheel (FW), 22 ... Decompression container, 23 ... Exhaust device, 24 ... Isolation valve, 25 ... Pressure converter, 26 ... Tachometer, 27 ... Rotation speed converter , 28 ... Measurement line penetration, 29 ...
Power line penetration, 31 ... Reactor vessel, 32 ... Motor casing / nozzle, 33 ... RIP impeller, 34
... Housing, 35 ... Stator, 36 ... Rotor, 37 ...
Journal bearing, 38 ... Thrust bearing, 39 ... Thrust plate built-in auxiliary pump, 40 ... RIP cooling water pipe, 41
... RIP cooling heat exchanger, 42 ... RIP cooling heat exchanger primary side, 43 ... RIP cooling heat exchanger secondary side, 44 ... Refrigerant piping, 45 ... Refrigerator, 46 ... Chilled water circulation pump, 47 ... Regenerator, 48 ... Regenerator for regenerator, 49 ... Refrigerant circulation pump for regenerator, 51 ... Chilled water piping, 52 ... Chilled water circulation pump, 53 ... Seawater cooling heat exchanger, 54 ... Seawater heat transfer tube, 55 ... Chilled water heat transfer tube, 56 ... Seawater piping , 57 ... Seawater pump, 59 ... Air cooling heat exchanger, 60 ... Air blowing fan, 62 ... Regenerator or refrigerator cooling heat exchanger, 63 ... Switching control valve, 65 ... Thrust plate, 66 ... Cooling water circulation pump, 67 Cooling water pump switching valve, 70 ... Flow rate adjusting valve, 71 ... Cooling water flow rate control device, 73 ... Circulating refrigerant control device, 75 ... Superconducting energy storage device (SMES), 76 ... Superconducting energy storage device controller, 78 ... Induction Electric Machine driven AC generator (MG),
80 ... Reactor cleaning system non-regenerative heat exchanger, 81 ... Cooling water distribution valve, 82 ... Seawater heat exchanger bypass valve S ... Instantaneous power failure or AC bus power loss signal, R ... Pump speed signal, F ... Pump speed command signal , P ... Flywheel inverter control signal, V ... AC bus power failure signal, N ...
RIP rotation speed signal, I ... Underwater induction motor current signal,
W ... Underwater induction motor input signal, K ... Valve opening signal, T ...
RIP cooling water temperature signal, C ... Refrigerant circulation pump control signal.

 ─────────────────────────────────────────────────── ─── Continuation of front page (72) Inventor Hideo Omida 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Stock company Toshiba Yokohama office

Claims (16)

[Claims] 1. Driving power is supplied from an in-house AC bus to a submersible induction motor driven recirculation pump (hereinafter referred to as RIP) with a built-in reactor through a variable voltage variable frequency power supply device (hereinafter referred to as VVVF), Induction electric drive of a flywheel energy storage device (hereinafter referred to as FMES) by obtaining AC power from the rectifier output side of the VVVF through an inverter device (hereinafter referred to as INV) by inverse conversion.
A flywheel (hereinafter referred to as FW) that is supplied to a generator (hereinafter referred to as IMG) and is directly connected to the rotating shaft of this IMG.
Is kept rotating at a predetermined number of revolutions, and the RIP operation necessary for suppressing thermal damage to the fuel rods loaded in the reactor at the time of instantaneous power failure or loss of power of the in-station AC bus can be continued. In the RIP drive power supply device that stores energy as inertial energy, the IM is generated by a signal of instantaneous power failure or power loss of the in-house AC bus.
Operate G as a generator by the current remaining in the circuit,
The inertial energy stored in the FW is converted into AC power, and a DC voltage is supplied via an INV controlled by the control device so that the VVVF outputs an AC voltage having a frequency corresponding to the operating speed of the RIP. A boiling water reactor built-in coolant recirculation device characterized in that the RIP operation can be continued for a predetermined time by converting it into electric power and supplying it to a DC circuit on the rectifier output side of VVVF. 2. RI from the in-house AC bus via VVVF
A driving power is supplied to P and a superconducting energy storage device (hereinafter, SMES) is supplied from the rectifier output side of the VVVF.
The energy required to suppress thermal damage to the fuel rods loaded in the reactor during the momentary power failure of the in-house AC bus or loss of power, and to continue the operation of the RIP. Store R
In the power supply device for IP drive, the energy obtained from the SMES is converted into AC power by the signal of the momentary power failure or the power loss of the in-house AC bus, and the RIP operation is predetermined by supplying it to the DC circuit on the rectifier output side of the VVVF. A boiling water reactor built-in coolant recirculation system characterized by being able to continue for only time. 3. The RIP drive power supply unit supplies drive power to a plurality of RIPs installed in a boiling water reactor, and at the time of instantaneous power failure or power loss of the in-house AC bus, the plurality of RIPs are supplied with atoms. 2. The boiling water reactor according to claim 1, wherein the energy required for continuing the operation of the RIP for suppressing the thermal damage of the fuel rods loaded in the reactor is stored in the FMES. Built-in coolant recirculation device. 4. A plurality of Rs installed in a boiling water reactor
Part of the IP is driven by the RIP drive power supply device, and the rest is F
The boiling water reactor built-in type coolant recirculation device according to claim 2 or 3, which is driven by a VVVF having no MES or SMES. 5. The boiling water reactor built-in coolant according to claim 1, 3 or 4, wherein the IMG and FW of FMES are housed in a container that is vacuumed or depressurized. Recirculation device. 6. A refrigerant of a refrigerator or cold water cooled by the refrigerant is supplied to a cooling heat exchanger of a submersible induction motor (hereinafter referred to as WIM) for driving a RIP pump. Item 6. The boiling water reactor built-in type coolant recirculation device according to any one of items 1 to 5. 7. The RIP WIM cooling heat exchanger is supplied with a refrigerant or cold water cooled by heat exchange with a cold heat medium stored in a regenerator. 5. The boiling water reactor built-in type coolant recirculation device according to any one of 5 above. 8. The cold water cooled by a dedicated seawater cooling heat exchanger or an air cooling heat exchanger is supplied to the cooling heat exchanger of the RIP WIM. The boiling water reactor built-in type coolant recirculation device according to any one of items 1 to 5. 9. The boiling water reactor built-in type coolant recirculation apparatus according to claim 6, wherein the cold water for cooling the WIM is circulated by a pump directly connected to the WIM. 10. The cooling water recirculation apparatus for a boiling water reactor according to claim 6, wherein the cold water for WIM cooling is circulated by a cooling water circulation pump installed outside. . 11. The boiling water reactor built-in type coolant recirculation apparatus according to claim 10, wherein a plurality of cooling water circulation pumps are installed in parallel. 12. The circulation flow rate of the cooling water circulation pump is set to RIP.
The boiling water reactor built-in type coolant recirculation device according to claim 10 or 11, wherein the cooling water recirculation device is controlled according to the rotation speed or the drive current, drive voltage or drive power of the WIM. 13. The cold water temperature for WIM cooling is controlled according to the RIP rotation speed or the drive current, drive voltage or drive power of the WIM.
0. The boiling water reactor built-in coolant recirculation device according to any one of 0. 14. The number of RIPs is a maximum integer that does not exceed a quotient obtained by dividing a core flow rate for obtaining a rated output at the end of an operation cycle of a boiling water reactor by a rated maximum flow rate of the RIP. 14. The boiling water reactor built-in type coolant recirculation apparatus according to any one of claims 1 to 13. 15. A drive power is supplied from a local AC bus to a plurality of RIPs via a VVVF, and the VVV is supplied.
RIP operation necessary to suppress thermal damage to the fuel rods loaded into the reactor at the time of instantaneous power failure or loss of power of the in-house AC bus, by supplying power from the rectifier output side of F to FMES or SMES In a power supply device that stores energy to be continued as inertial energy or magnetic field energy, if one RIP fails, the control rods will have a core heat output that does not cause thermal damage to the fuel rods loaded in the core. Is inserted to reduce the reactor power and then repaired to recover the power, or if repair is not possible, there is no risk of thermal damage to the fuel rod loaded in the core until the scheduled shutdown of the reactor. A method of operating a boiling water reactor built-in type coolant recirculation device, characterized in that a control rod is inserted until the core heat output is reached, and the reactor output is reduced to continue operation of the reactor. 16. A heat exchanger for cooling a RIP WIM,
In a power supply device that supplies cold water cooled by a dedicated seawater cooling heat exchanger or air cooling heat exchanger,
If the cold water temperature obtained by the sea water cooling or air cooling heat exchanger is sufficiently low and the cold water at the predetermined temperature necessary for WIM cooling can be supplied through the WIM cooling heat exchanger, the sea water cooling or air cooling heat exchanger is activated. When the seawater or the atmospheric temperature is too high to supply the cold water having the predetermined temperature required for WIM cooling, the seawater cooling or the air cooling heat exchanger is not operated, and the refrigerant of the refrigerator or the cold water cooled by the refrigerant is used.
16. The boiling water reactor built-in type coolant recirculation device according to claim 15, wherein the coolant or the cold water cooled by heat exchange with the cold heat medium stored in the regenerator is supplied.