JPH0996695A - Drain treating facility for nuclear reactor - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a method and facility for treating drain in a nuclear reactor in which the drain of a main steam line can be treated without causing any hammering even if the main steam line is installed at a position relatively lower than a main condenser. SOLUTION: A flush tank 50 is installed at a position relatively lower than main steam lines 2, 5 and coupled through a channel with the discharge side end of a main steam drain line so that the main steam line drain is separated into steam phase and condensate phase in the tank 50. Upper part of the tank 50 is coupled with the main condenser 8 of a power generation steam turbine 7 and/or a redioactive liquid waste treating facility 34 through a channel extending continuously with an up grade or horizontal grade from the upper part of tank 50. The lower part of the tank 50 is coupled with the main condenser 8 and/or the treating facility 34 and a means for transferring the condensate in the tank 50 to the main condenser 8 and/or the treating facility 34 is disposed above the channel.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating a reactor steam condensing drain and a treatment apparatus therefor, in particular, the reactor is installed deep underground and the main condenser is installed near the ground level. The present invention relates to a reactor vapor condensation drain treatment method and treatment device for nuclear reactor equipment.

[0002]

2. Description of the Related Art In this type of nuclear reactor equipment, a main steam drain line for discharging and removing condensed liquefied water in the main steam line is installed in a main steam line, that is, a pipeline for supplying steam generated in the reactor to a steam turbine. It is usually equipped with.

A main steam drain treatment device for discharging steam drain generated by condensation of the reactor main steam in a pipeline to a suppression chamber is disclosed in, for example, JP-A-58-60297.
A main steam drain processing device disclosed in Japanese Patent Publication No. 58-60298 is disclosed in Japanese Patent Laid-Open No. 58-60298, and the main steam drain processing device is designed to collect the main steam drain in a tank installed below the main steam line.
No. 6,086,045.

[0004]

Conventionally, the main steam drain is usually finally collected in the main condenser, and the main steam drain can be collected in the main condenser. This is because the main condenser is conventionally arranged at a position relatively lower than the main steam condensation drain generation source. Therefore, when draining the seal water for the main steam isolation valve leak test, it is possible to transfer the drain by gravity, and also the two-phase flow drain flushed with the high temperature and high pressure drain generated after the nuclear reactor nuclear heating will also use the steam hammer. It was possible to transfer without the occurrence.

However, by introducing a new concept of equipment layout,
If the reactor is installed at a large depth of tens of meters underground and the main condenser is to be placed near the ground level, the conventional method cannot be applied as it is. In other words, it is no longer possible to transfer the sealed water for leakage test of the main steam isolation valve to the main condenser by gravity, and the high-temperature high-pressure drain generated after the nuclear reactor heating is flushed and the two-phase flow drain is flushed. However, it is still impossible to collect in the main condenser with continuous down-gradient piping that can reliably avoid steam hammers.

Drain generated in the reactor isolation cooling system was also collected in the main condenser in the past. However, in this case, the drain transfer line is not a continuous downward slope, but a maximum of about a maximum due to the equipment layout. There was a 5m rise. However, if this method is applied when installing a cooling system turbine for reactor isolation at a large depth of several tens of meters underground, the rise height of the drain line will also be several tens of meters, greatly exceeding the conventional results, so steam hammers etc. There is no certainty whether stable drain processing is possible without causing
This is because the applied technology having such a rising portion has experimental and empirical factors, in contrast to the basic technology of recovering in a downward slope.

The present invention has been made in view of the above problems, and an object thereof is to provide a gas-liquid two-phase pump even if the installation height of the main steam line is relatively low with respect to the main condenser. It is an object of the present invention to provide a method and an apparatus for treating a main steam drain of this kind, which is capable of treating a main steam drain without causing hammering due to a phase flow.

[0008]

That is, the present invention comprises a main steam line for supplying main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from the main steam line. A reactor steam condensation drain treatment facility that is configured to discharge and remove condensed liquefied water in the steam line from the main steam line to the main steam drain line, or in addition to the main steam line and the main steam drain line, Reactor isolation cooling system steam line that supplies the steam generated in the reactor to the reactor isolation cooling system driving steam turbine, and the reactor isolation cooling system steam drain line branched from this reactor isolation cooling system steam line The liquefied water in the reactor isolation cooling system steam line is discharged and removed from the reactor isolation cooling system steam line to the reactor isolation cooling system steam drain line. In the reactor steam condensation drain treatment facility formed in, in the middle of the main steam drain line flow path, and in the middle of the reactor isolation cooling system steam drain line flow path, drain discharge amount A restricting orifice, a steam trap, or a control valve is provided, and a flash tank is provided at a position relatively lower than the main steam line, and the discharge side end of the main steam drain line is provided in the flash tank, or ,
The discharge side end of the reactor isolation cooling system steam drain line, or both the discharge side end of the main steam drain line and the discharge side end of the reactor isolation cooling system steam drain line, The main steam drain and / or the steam drain for the cooling system during reactor isolation, or both, are configured to be separated into a vapor phase and a condensed water phase in a flash tank, and the upper part of the flash tank and the power generation. The main condenser of the steam turbine for operation is connected to the main condenser from the upper part of the flash tank through a flow path that connects continuously with an upward slope or a horizontal slope. Main condenser of turbine or lower part of flash tank and radioactive liquid waste treatment facility, or lower part of flash tank and main condenser of steam turbine for power generation A pump having the ability to connect both the radioactive liquid waste treatment equipment via a flow path and to transfer the condensed water in the flash tank to the main condenser or the radioactive liquid waste treatment equipment on this flow path. It is designed to achieve the intended purpose.

The present invention will be summarized and described in a little more detail. (1) As a drain transfer means, there are cases where the two-phase flow is carried as it is, gas-liquid separation is carried, and condensed water is carried. However, which is to be used is determined by comprehensively considering various conditions in each plant plan.

1a. When transferring as a two-phase flow, first, with respect to the main steam drain, the drain pipe is continuously downwardly or horizontally inclined to the suppression chamber toward the suppression chamber at a position lower than the main steam drain discharge position. Guided and submerge the open end of the drain line in the suppression pool.

The drain flow rate is controlled by a flow rate limiting orifice provided in the drain line, a flow rate limiting mechanism such as a steam trap,
And these are set appropriately using a bypass line.
That is, while the reactor is still at a low pressure in the early stages of nuclear reactor heating, the flow restriction mechanism is bypassed to ensure the drain discharge capacity when the amount of condensed drain is large because the system is in the process of warming up. In addition, the main steam drain flow rate is limited by using the flow rate limiting mechanism at the time when the reactor is at the rated pressure from the end of reactor nuclear heating to the plant operation, warming up is completed, and the amount of condensed drain is small. Regarding the above drain flow rate limitation, in the other case of the present invention, that is, when a means for separating and transferring gas-liquid or a means for transferring as condensed water is used, and when the drain is transferred to the main condenser The same applies to the above.

As for the drainage system for the cooling system during reactor isolation, the drain discharge position is lower than the suppression pool water level, so the drain piping should first be raised above the suppression pool water level and then connected to the suppression chamber.
Submerge the open end of the drain line in the suppression pool. The drain piping is equipped with a vacuum breaking mechanism such as a vacuum breaking valve or a vent hole inside the suppression chamber to prevent negative pressure inside the drain piping due to vapor condensation and sucking up the suppression pool water and backflowing through the drain line. To

1b. In the case of gas-liquid separation and transfer, the drain is once introduced to a drain recovery container such as a flash tank or a drain pot, where it is separated into flash vapor and condensed water. The drain recovery container has a vent pipe communicating with the main condenser, so that the internal pressure is kept almost constant, and the flash steam and the condensed water have the generated amount and temperature corresponding to the internal pressure. The flash steam is taken out upward from here, and is continuously introduced into the main condenser through an upward or horizontal gradient vent pipe. Condensed water is taken out downward from the drain recovery container and is guided to the main condenser by increasing the pressure with a pump as necessary.

1c. In the case of transferring as condensed water, in this case, the total amount of the two-phase flow drain is changed to the condensed water drain by the water-cooled steam condenser, and then the main condenser is boosted by a pump if necessary. Be led to.

(2) As the reactor degassing means, the present invention shows several different means as follows. These means are independent of each other, and which means should be used should be decided in consideration of common use with the above-mentioned two-phase flow drain transfer facility in individual plant planning.

2a. In the case of deaeration using the turbine bypass line, in this case, after the main condenser vacuum level rises, the main steam isolation valve and turbine bypass line are opened, and the main reactor is restored via the main steam line and turbine bypass line. It is a device that communicates with a water vessel to degas. As a method of opening the turbine bypass line, a method of opening a turbine bypass valve and a method of providing a remote control valve for deaeration on the turbine bypass line and opening this valve are considered. This method is particularly effective when the main steam drain line is not connected to the main condenser.

2b. When degassing using the main steam drain line connected to the main condenser, in this case, open the main steam drain line connected to the main condenser after the main condenser vacuum level rises, and connect the main steam drain line. The reactor is communicated with the main condenser via the degasser.

At this time, the main steam drain line used for degassing is constructed so as not to be blocked by the condensing drain and not interfere with degassing. That is, since the equipment for separating the main vapor drain of the two-phase flow by gas-liquid separation has the vent line for transferring the gas phase portion, this is also used as the degassing line. In addition, in the case where the vent line for transferring the gas phase part is not provided, since the line for transferring the liquid phase part is used as the degassing line, a line dedicated for degassing is provided at the bottom of the line for transferring the liquid phase part. A U-seal type drain line is provided,
There is a method of degassing condensed water in the main steam drain line while draining the condensed water through the U-seal while using the liquid phase transfer line. Here, the U-seal prevents the intake of air into the main condenser.

(3) As means for confining radioactive material,
In the present invention, the open ends of the main steam drain transfer system and the reactor isolation cooling system steam condensation drain transfer system are limited to the main condenser, the suppression chamber, and the radioactive waste treatment facility. By not doing so, we confined the radioactivity.

(4) As means for maintaining the water temperature / water level of the suppression pool, when recovering the main steam drain or the drainage system for cooling during reactor isolation in the suppression pool, means for maintaining the suppression pool at a predetermined water temperature / water level. is necessary. In the present invention, the following means are used to appropriately maintain the water temperature / water level.

4a. As a method of pre-cooling the drain and collecting it in the suppression pool, a water-cooled steam condenser is installed to condense the steam, and this drain is used with this steam condenser or a separate drain cooler to adjust the drain to the normal water temperature of the suppression pool. Cool to equivalent temperature and collect in suppression pool.

4b. As a method of activating the suppression pool cooling mode of the residual heat removal system, activate the suppression pool cooling mode of the residual heat removal system as necessary,
Maintain the suppression pool water at the desired temperature.

It should be noted that, in this mode, conventionally, the frequency of starting is low and the mode is only started during a regular test for confirming the soundness of the residual heat removal system, and the starting operation was manual. When high-temperature drains are continuously discharged to the suppression pool during plant operation according to the present invention, the start-up frequency of this mode increases, so it is conceivable to automate the start-up operation. The range of automation will be selected mainly in consideration of economical efficiency, but when the entire range of operation is automated, it is as follows. That is, the suppression pool water temperature is constantly measured, and when the pool water temperature reaches an appropriately set temperature, the control device issues an automatic start signal for this mode, which causes the residual heat removal system and the auxiliary cooling water system that is the related system. Automatically start the suppression pool cooling mode of.

4c. As a method of activating the suppression pool water transfer mode of the residual heat removal system, the suppression pool water transfer mode of the residual heat removal system is activated as necessary to maintain the suppression pool at a predetermined water level.

In this mode, the activation frequency is low and the activation operation is manual. In the case where the drain is continuously discharged to the suppression pool during plant operation according to the present invention, the starting frequency of this mode increases, so it is conceivable to automate the starting operation. The scope of automation is
It will be selected mainly in consideration of economy.

(5) As protection against overpressure, the main steam drain recovery equipment and the reactor isolation cooling system drain recovery equipment are connected to the high pressure reactor line, so care must be taken to prevent damage from overpressure. is there. In the present invention, an appropriate method is selected and used from the following methods.

By providing a line for connecting the gas phase part of the drain recovery container to the main condenser and not providing any valve that may close the line on the way, the internal pressure of the drain recovery container is always restored to the main pressure. Pour into a water vessel. A method of installing a safety valve in the drain collection container or drain collection line, and connecting the exhaust line of the safety valve to the main condenser or suppression chamber.

An interlock is provided to constantly measure the pressure in the drain recovery container or the drain recovery line and automatically close the valve provided in the drain line when the pressure is abnormally high to prevent overpressure. The pressure resistance design condition of the drain recovery container or drain recovery line should be equivalent to the reactor design pressure.

(6) Main condenser As a vacuum break prevention in the present invention, in the present invention, air is accidentally introduced from the steam drain line to the main condenser.
Select an appropriate one from the following methods so that nitrogen is sucked in and the vacuum of the main condenser is not broken.

The steam drain line has no open end other than the drain source and the main condenser. Submerge the open end of the steam drain line on the suppression pool side. A U-seal that has a sealing function against a differential pressure of 10 m or more of water column is provided, which can prevent communication between the main condenser and the open end of the atmosphere such as a suppression chamber. Appropriate monitoring devices and interlocks will be provided to prevent loss of U-seal functionality.

Next, the operation of the device thus formed will be described.

(1) Regarding the discharge of the sealing water used in the main steam isolation valve leakage test, in the present invention, the sealing water used in the test after the main steam isolation valve leakage test is relative to the main steam isolation valve. It is discharged by gravity into a suppression pool provided at a low position or a drain recovery container such as a flash tank. The water discharged to these is pumped from here to the main condenser or radioactive waste treatment facility.

(2) Regarding degassing of non-condensable gas and treatment of condensed drain during reactor degassing operation In the present invention, the non-condensable gas and condensed drain produced during reactor degassing operation are routed separately. Will be collected at. This is because in the case of a plant in which the reactor is installed at a relatively deeper depth than the turbine, when trying to suck non-condensable gas and condensed drain into the main condenser at the same time with a single line, it will rise in the middle. This is a method taken to prevent the condensed drain from being accumulated in the pipe and blocking the line, so that the non-condensable gas cannot be sucked.

(3) Drain recovery during normal plant operation after the start of nuclear reactor heating In the present invention, the drain generated during normal plant operation after the start of nuclear reactor heating is recovered in the main condenser or suppression chamber. .

A. When recovering to the main condenser, the high pressure drain equivalent to the reactor pressure is decompressed in the middle to generate a two-phase flow, but the drain is transferred from the reactor side at a relatively low position to the turbine side at a high position. To achieve this, a recovery method that does not cause steam hammer is required. In the present invention, in the case of collecting in the main condenser, a flash tank or a drain pot is provided, and a method of separating and collecting gas and liquid here, and
A method was proposed in which a water-cooled steam condenser was installed to condense the steam and recover the entire drain as condensed water. Steam hammer is a phenomenon in which condensed water accumulated in the pipe is accelerated into a high-speed steam flow and collides with a bend in the pipe.Therefore, gas-liquid is separated and collected, and the collected part of condensed water is collected in the steam recovery line. It is possible to prevent the generation by eliminating all or by condensing all the vapor contained in the two-phase flow drain.

Condensed water can be transferred from a drain recovery container such as a flash tank to the main condenser by a pump, or by maintaining an appropriate pressure difference between the drain recovery container and the main condenser. A method of transferring by utilizing this pressure difference was adopted.
Maintaining an appropriate pressure inside the drain recovery container is important from the following points.・ Withstand pressure design of drain collection container and piping system ・ Pump NPS for transferring condensed water by pump
Securing H, and securing pumping capacity in the case of transferring condensed water by the pressure difference between the drain collection container and the main condenser.

Therefore, in the present invention, as a method for maintaining the inside of the drain recovery container at an appropriate pressure, an appropriate method is selected from the following methods. To secure the pumping capacity for the above-mentioned transfer of condensed water, the following method b) or d) is used.

A) A line for connecting the gas phase part of the drain recovery container and the main condenser is provided to allow flush steam to pass, and the drain recovery container pressure is almost equal to the main condenser pressure, strictly speaking, the flow of the line. Keep the pressure higher than the main condenser by the amount of resistance.

B) A line for connecting the gas phase part of the drain recovery container and the main condenser is provided to allow flush steam to pass through, and a control valve for adjusting the pressure on the drain recovery container side is provided on the line. , Keep the drain recovery vessel pressure at the main condenser pressure plus the flow resistance of the line including the control valve.

C) A line for connecting the vapor phase portion of the drain recovery container and the vapor phase portion of the suppression chamber is provided to keep the drain recovery container pressure substantially equal to the suppression chamber pressure.

D) By forcibly condensing the steam in the steam condenser, a flow is constantly generated in the main steam drain line, and a fluid pressure drop is caused by a flow rate limiting orifice provided in the middle of the line. The drain recovery container pressure is maintained at the reactor pressure minus the pressure drop due to the flow restriction orifice.

B. When the main steam drain is recovered in the suppression chamber, since the drain generation source is relatively higher than the suppression pool, it is possible to directly introduce and condense the two-phase flow drain into the suppression pool. It is also possible to condense the steam with a water-cooled steam condenser in advance and then discharge the steam into the suppression pool.

When collecting the drainage in the reactor isolation cooling system into the suppression chamber, the drainage source is relatively lower than the suppression pool, but the two-phase flow drain is suppressed at a start-up height within the range of the preceding machine performance. It is possible to take the method of directing and condensing directly to the pool. It is also possible to condense the steam with a water-cooled steam condenser in advance and then discharge the steam into the suppression pool.

[0044]

DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention will be described below in detail with reference to the illustrated embodiments. FIG. 1 shows the system of the steam condensate drain treatment device. This figure shows the state during normal operation of the plant (the relationship between the valve open / closed state and the line thickness). The thick lines in the figure represent the lines used for drain transfer, deaeration, etc. in each operation mode.The valve symbols are the open ones for the white parts and the closed ones for the black parts. It shows the state.

In the figure, reference numeral 1 is a nuclear reactor, and steam generated in the nuclear reactor is supplied to a steam turbine 7 through main steam lines 2 and 5, and the steam turbine drives the steam turbine. Reference numeral 8 installed in the lower portion of the steam turbine is a main condenser 8. Drain lines 10 and 16 are provided in the main steam lines 2 and 5 inside and outside the reactor containment vessel so that the generated steam condensation drain is discharged, and in the steam piping 23 of the reactor isolation cooling system, A drain pot 24, a steam trap 31, and a drain line 30 are provided so that the generated vapor drain is discharged.

The recovery lines 20 and 30 for the main steam drain and the reactor isolation cooling system drain are connected to the flash tank 50 installed in the lower portion. In addition, the flash tank 50 has a vent line 51 that connects the gas phase portion at the top of the tank and the main condenser 8 with a continuous upward slope toward the main condenser, and a condensation drain that discharges condensation drain from the bottom of the tank. A drain line 53 is provided.

The condensed drain line 53 is connected to the main condenser 8 or the liquid waste treatment facility 34 via the condensed water transfer pump 54, and the transfer destination switching valve 56, is connected to the line.
57 and check valves 62, 63 are provided. Also,
A water level gauge 52 is provided in the flash tank 50 and is used to control the condensed water transfer pump 54.

The main steam drain lines 10 and 16 are provided with flow limiting orifices 14 and 18 and their bypasses 15,
After merging into one line downstream of 19, it is branched into a flash tank side line 20 and a suppression pool side line 58. The suppression pool side line 58 is provided with a containment vessel isolation valve 59 and a check valve 61, the tip of the line is lowered to a level below the normal water level of the suppression pool 33, and the open end is submerged.

(1) Next, a method for operating the drain treatment device thus formed will be described along with a procedure for starting the plant.

A) Regarding drainage after leakage test of main steam isolation valve, FIG. 2 shows drainage of main steam piping after completion of leakage test of main steam isolation valve which is carried out prior to reactor startup at the end of plant periodic inspection. The state at the time of operation is shown. In the main steam isolation valve leak test, the main steam isolation valves 3 and 4 were fully closed,
The main steam pipe 2 upstream of the inner main steam isolation valve 3 is filled with water for water sealing. After the test, in order to drain water from the main steam pipe 2, the main steam drain line isolation valve 11,
12, the orifice bypass valve 15 and the suppression chamber side drain valve 59 are fully opened, the flash tank side drain valve 60 is fully closed, and water is discharged to the suppression chamber 33. In addition to the above-described method, the method of draining water from the main steam pipe is not limited to the above-described method, and the radioactive liquid waste treatment facility 3 is operated via the flash tank 50 and the drain transfer pump 54.
4 or the main condenser 8 can also be drained.

B) Regarding the reactor deaeration operation, FIG. 3 shows the state during the reactor deaeration operation prior to the reactor startup. The main steam drain line isolation valves 11 and 12, the orifice bypass valve 15 and the flash tank side drain valve 60 are fully opened to suck the dissolved oxygen contained in the water held in the reactor 1 by the vacuum of the main condenser 8. The suppression chamber side drain valve 59 is fully closed. As a result, the dissolved oxygen in the reactor is converted into the main steam pipe 2, the main steam drain pipe 10, the flash tank 50, and the flash tank vent pipe 51.
And is sucked into the main condenser 8.

C) In the early stage of nuclear heating of the nuclear reactor, FIG.
At the early stage of nuclear heating after the completion of degassing of the reactor, the reactor pressure is lower than the rated pressure, and the main steam pipes 2 and 5 and the main steam isolation valves 3 and 4 are in the process of warming up to generate steam condensation drain. Since the amount is larger than that in the rated operation, in order to secure the drain discharge capacity that exceeds the generated drain amount, the orifice 1
4 shows the operating state at the time when it is necessary to bypass 4,18.

The drain flowing into the flash tank 50 from the main steam drain pipes 10 and 16 is separated into flash steam and condensed water, and the flash steam is vent pipe 5
1, the condensed water is collected in the main condenser 8 by the drain transfer pump 54. The flash tank 50 has a vacuum degree of about 7
The temperature of steam and condensed water generated by flashing is about 40 ° C., because the main condenser 8 of 00 mmHg is vented and the degree of vacuum is kept almost the same.

The water level in the flash tank is detected by the water level gauge 52, and in order to maintain the water level in an appropriate water level range, the drain transfer pump 54 receives the water level signal and automatically performs automatic ON-OFF operation or rotation speed control operation. Perform control operation. At this time, the reactor isolation cooling system is also warming up, and drain is discharged to the flash tank 50 through the drain pot 24, the steam trap 31, and the drain line 30.

D) FIG. 1 shows the normal operation of the plant.
After the latter half of nuclear reactor heating, during plant operation,
The operating state is shown during a period in which a drain discharge capacity exceeding the generated drain amount can be secured without bypassing the orifice 18. Here, the inner main steam drain line 10 is closed and only the outer main steam drain line 16 is used as follows.

The orifice bypass valve 19 is fully closed, the orifice inlet valve 17 is fully opened, and the flash tank 50 receives the drain. The drain flowing into the flash tank 50 is separated into flash steam and condensed water, and the flash steam is collected in the main condenser 8 by the vent pipe 51 and the condensed water by the drain transfer pump 54. The water level in the flash tank is detected by the water level gauge 52, and the operation of the drain transfer pump 54 is controlled to keep the water level in an appropriate water level range.

Further, since the line 23 for supplying steam to the steam drive turbine 26 of the reactor isolation cooling system during the normal operation of the plant stands by in a warm-up state, condensation drain occurs, and this drain also drains the drain pot 24, It is discharged to the flash tank 50 via the steam trap 31 and the drain line 30.

(2) The control / interlock will be described as follows: a). As described above, the water level of the flash tank is detected by the water level gauge 52, and in order to keep this in an appropriate water level range,
The drain transfer pump 54 receives the water level signal and automatically turns on and off.
Perform automatic control operation such as FF operation or rotation speed control operation.

B). The stop valve 60 on the flash tank side and the stop valve 59 on the suppression pool side are provided with an interlock so that they are not opened simultaneously.

C). The main condenser side stop valve 56 and the liquid waste treatment system side stop valve 57 are provided with an interlock so that they are not opened simultaneously.

(3) Considering the consideration of trapping radioactive material, in this embodiment, the open end of the drain recovery system is limited to the suppression chamber 33, the main condenser 8 and the liquid waste treatment facility 34. . All of these are facilities that can safely handle radioactive fluids, and can process radioactive substances without releasing them to the outside of the system.

(4) In relation to overpressure protection, the flash tank 50 is always connected to the main condenser 8 via the vent line 51, which releases pressure so that it may be overpressurized. Absent.

(5) Regarding prevention of vacuum breakage of the main condenser, in the present embodiment, the following consideration is given to the suppression pool connection line and the liquid waste treatment equipment connection line where the main condenser 8 is connected to the line. By doing so, the vacuum break of the main condenser is prevented. That is, the suppression pool connection line 58 should be submerged at the tip, the isolation valve 59 should be fully closed when the stop valves 56 and 60 connected to the main condenser are open, and the check valve 61 should be provided. Prevents the intake of air and nitrogen from the suppression pool side.

A stop valve 57 and a check valve 63 are provided in the liquid waste treatment equipment connection line, and the stop valve 57 is fully closed when the stop valve 56 connected to the main condenser is open. , Prevent inhalation of air. The stop valves 56, 5
An interlock corresponding to the above valve operation is provided between 7, 59 and 60.

Next, another embodiment will be described with reference to FIG. The present embodiment is provided with a flash tank that is kept at a higher pressure than the main condenser, and separates the drain into flash steam and condensed water and collects it in the main condenser.

The main tank drain line 20 and the reactor isolation cooling system drain line 30 are provided in the flash tank 50.
Connect. In the flash tank 50, a vent line 51 that connects the gas phase portion at the upper part of the tank and the main condenser 8 with a continuous upward gradient toward the main condenser, and a line 53 that discharges condensed drain from the lower part of the tank. To provide. The vent line 51 is provided with a safety valve 83 and a pressure control valve 80. The exhaust of the safety valve 83 bypasses the pressure control valve 80 and is connected to the main condenser 8. A water level control valve 82 is provided on the main condenser side line of the condensed water transfer line 53. The flash tank is equipped with a pressure gauge 81 and a water level gauge 52, and each has a control valve 8
Used to control 0, 82.

Further, the flash tank is provided with a drain line 85 and a drain valve 84 used for deaeration, and this drain line is connected to the drain sump. The main steam drain lines 10, 16 have flow limiting orifices 14, 18, and
After merging into one downstream of these bypasses 15 and 19, they are branched into a flash tank side line 20 and a suppression pool side line 58. The containment vessel isolation valve 59 and the check valve 6 are provided in the suppression pool side line 58.
1, the tip of the line is lowered to a level below the normal water level of the suppression pool 33, and the open end is submerged.

(1) The operating method is as follows.

A). Drain water after leak test of main steam isolation valve. In this embodiment, drainage after the main steam isolation valve leak test is performed by draining the water to the pool using the suppression pool side drain line 58 as in the above-described embodiments.

B). Regarding the deaeration operation of the reactor, the deaeration operation of the reactor is performed by fully opening the flash tank pressure control valve 80. Drain generated during deaeration is discharged to the drain sump through the drain line 85 provided at the bottom of the flash tank. During the deaeration operation, the drain valve 84 receives a signal from the water level gauge 52 and automatically opens and closes so as to keep the tank water level within a predetermined range. At this time, since the flash tank 50 has a pressure almost equal to that of the main condenser 8, the temperature of the flushed steam and condensed water is about 40 ° C., and the drain can be discharged to the drain sump which is not of high temperature specifications. It is possible.

C). If the reactor pressure starts to rise in the early stage of nuclear reactor nuclear heating and the condensed drain in the flash tank 50 can be pumped up by the differential pressure with the main condenser 8 and transferred to the main condenser 8, The deaeration drain valve 84 that had been automatically opened and closed until then is fully closed, and the automatic control operation of the control valve 82 by the water level gauge 52 and the automatic control operation of the control valve 80 by the pressure gauge 81 are started. At this time, the control set value of the flash tank pressure is determined so that the drain pumping capacity corresponding to the installation level difference between the flash tank 50 and the main condenser 8 can be secured.

For example, if the installation level difference between the two is 30 m, and the flow resistance of the condensed water transfer line including the water level control valve 82 is equivalent to 10 m of water column, the total pumping capacity of 40 m of water column is approximately equivalent to differential pressure conversion. 0.4 MPa is required and the flash tank pressure setting is 0. 1 for the vacuum main condenser.
It becomes 4 MPa higher and the absolute pressure becomes 0.4 MPa. The water level control valve 82 operates to keep the flush tank water level constant.

D). Regarding the normal operation of the plant, during the normal operation of the plant, the same operation as that after the initial stage of the nuclear reactor nuclear heating is performed.

(2) Regarding interlock, a). Flash tank drain valve 8 during reactor deaeration operation
4 receives the signal from the water level gauge 52 and repeats automatic opening and closing so as to keep the tank water level within a predetermined range.

B). After the nuclear reactor heating, pressure control valve 80
Receives a signal from the pressure gauge 81 and keeps the tank pressure constant.

C). Water level control valve 82 after nuclear reactor heating
Receives a signal from the water level gauge 52 and keeps the tank water level constant.

D). The flash tank inlet valve 60 receives the abnormal pressure high signal from the pressure gauge 81 and automatically closes.

(3) Regarding overpressure protection, in the unlikely event that the pressure control valve 80 or the like fails and the flash tank pressure exceeds an appropriately set value, the flash tank inlet valve 60 is turned off by a signal from the pressure gauge 81. Fully closed protects the flash tank from excessive pressure. Also, pressure gauge 8
For the failure of No. 1, the safety valve 83 protects against overpressure.

Next, another embodiment will be described with reference to FIG. In this embodiment, a flash tank and a steam condenser are provided, and all the drain is collected as condensed water in a condenser. The flash tank 50 has a main steam drain line 20 and a reactor isolation cooling system. Connect the drain line 30. The flash tank 50 is provided with a vapor line 70 that connects the vapor phase portion at the top of the tank and the vapor condenser 71, and a line 53 that discharges condensed drain from the bottom of the tank.

The steam condenser 71 is a flash tank 50.
The steam flowing in through the line 70 from is condensed by the cooling water 73. The condensed water returns to the flash tank 50 through the line 72. The line 72 forms a U-seal, which keeps the water level in the steam condenser constant. The highest position of the vapor phase part of the steam condenser 71 and the U-seal is at the vent lines 74 and 75 at the suppression chamber 3
Connect to 3. The reactor containment vessel isolation valves 76 and 77 are provided in this vent line. The condensate drain line 53 is connected to the main condenser 8 or the liquid waste treatment facility 34 via the condensate transfer pump 54, and the transfer destination switching valves 56 and 57 and the check valves 62 and 63 are connected to the line. To provide.

The flash tank 50 is the main condenser 8
The drain transfer line 53 is maintained at a level lower than at least 10 m so that the drain transfer line 53 maintains a full state even during a normal operation in which the main condenser 8 becomes a vacuum equivalent to about 10 m of water column and sucks the condensed drain. This is a consideration for preventing the suppression chamber 33 and the main condenser 8 from communicating with each other. Further, the flash tank 50 is provided with a water level gauge 52, which is used for controlling the condensed water transfer pump 54. The main steam drain lines 10 and 16 are flow restricting orifices 14 and 1,
8 and these downstream bypasses 15 and 19 merge into one.

(1) The operating method is as follows.

A). Drain water after leak test of main steam isolation valve. The waste water after the main steam isolation valve leak test is received by the flash tank 50 and transferred to the main condenser 8 or the liquid waste treatment system 34 by the drain transfer pump 54.

B). The reactor deaeration operation is performed by fully opening the main steam isolation valves 3 and 4 and slightly opening the turbine bypass valve 9.

C). Drain flowing into the flash tank 50 during nuclear reactor heating-normal plant operation is
Here, the vapor and liquid are separated, and the vapor passes through the line 70 to the vapor condenser 71, is cooled by the cooling water 73 to become condensed water, passes through the line 72, and returns to the flash tank 50.

Here, the flash tank 50 has a vent 7
Suppression chamber 33 at atmospheric pressure through 4, 75
The flash steam and condensed water generated are about 100 ° C. The condensed water accumulated in the flash tank 50 is transferred to the main condenser 8 by the drain transfer pump 54.

(2) Regarding prevention of vacuum breakage of the main condenser, in this embodiment, the rising height of the drain transfer pipe from the flash tank 50 to the main condenser 8 is secured to be 10 m or more. As a result, a water column is formed in this part to have a sealing function, and the main condenser 8 is operated by the suppression chamber 3
Make sure that nitrogen gas is not sucked from 3 to break the vacuum.

Next, another embodiment will be described with reference to FIG. In this embodiment, all the drain is collected in the suppression pool, and the main steam drain lines 10 and 16 are put together in a line 58 connected to the suppression pool, and the tip is submerged. The flow rate limiting mechanism installed in the main steam drain line is a steam trap 92, 9
3, the drain discharge flow rate to the suppression pool is minimized to the necessary minimum.

The drain line 30 for cooling system during reactor isolation is
Start up above the suppression pool level and connect to it to submerge the tip. In the drain line 30,
A vacuum break valve 98 is provided in the portion of the suppression chamber 33 where the line is not submerged in water. The suppression pool water temperature gauge 91 sends a signal to the control device 94 to automatically start the suppression pool cooling mode of the residual heat removal system at a high water temperature. The suppression pool water level meter 90 sends a signal to the control device 94 to automatically activate the suppression pool water drainage mode of the residual heat removal system at a high water level to transfer the pool water to the liquid waste treatment system. In addition, a turbine bypass small valve 95 dedicated to reactor deaeration is provided in parallel with the turbine bypass valve.

(1) The operation method is as follows.

A). Regarding the drain processing, in the present embodiment, all the main steam drain and the reactor isolation cooling system drain generated during the normal operation from the plant start preparation are collected in the suppression chamber. Due to drain inflow,
When the water temperature or water level of the suppression pool becomes higher than a predetermined level, the suppression pool cooling mode of the residual heat removal system or the suppression pool water drainage mode is automatically activated.

B). In the reactor deaeration operation, the main steam isolation valves 3 and 4 and the turbine bypass small valve 95 are fully opened in order to suck the dissolved oxygen contained in the water held in the reactor 1 by the vacuum of the main condenser 8. As a result, the reactor dissolved oxygen is sucked into the main condenser 8 through the main steam pipes 2 and 5 and the turbine bypass small valve 95. The turbine bypass small valve 95 is a general valve having the same capacity as the main steam drain valve 11, while the turbine bypass valve 9 is a special valve that has a large capacity and operates at high speed and is more complicated in operation than a general valve. , Provided so that deaeration can be performed with a simple operation. The reactor deaeration operation is performed by fully opening the main steam isolation valves 3 and 4 and opening the valve 95 dedicated to the reactor deaeration provided in the turbine bypass line.

Next, another embodiment will be described with reference to FIG. In this embodiment, the main steam drain of the two-phase flow is collected as condensed water in the main condenser using a water-cooled drain cooler, and the installation position of the reactor isolation cooling steam turbine is suppressed. Above the pool water level, the drain line is led to the suppression pool with a downward slope.

That is, the main steam drain line is 10, 1
After being combined into one, 6 is branched into a line connected to the drain cooler 100 and a line 58 connected to the suppression pool. In the drain cooler 100, the cooling water 1
01, and the condensed water is collected in the main condenser 8 through the transfer line 102. A mechanism for limiting the main steam drain flow rate is a control valve 112, which receives a signal from the pressure gauge 81 to keep the pressure of the drain cooler constant.

At the lowest position of the transfer line 102, a U-seal 10 provided for drain discharge during degassing operation of the reactor.
7, U seal inlet valves 104 and 105, a thermometer 106, and a seal water supply valve 109 are provided. Also, the drain cooler 10
A pressure gauge 81 is provided at 0 so that the drain cooler inlet valve 60 can be closed at an abnormally high pressure.

Steam turbine 26 of the reactor isolation cooling system
Conventionally, it was installed at the same height as the bottom of the suppression pool 33, but in this embodiment, this is installed at a position higher than the water level of the suppression pool. Conventionally, the steam turbine 26 was installed at a low position equivalent to the bottom of the pool because the N of the pump installed integrally with the steam turbine 26.
This was to secure PSH. That is, N of the pump
This is because, from the viewpoint of PSH, it was advantageous that the pump position was relatively low with respect to the water source position.

However, in the plant in which the reactor to which the present invention is applied is installed deep in the ground, if the tank serving as the water source of the cooling system during the reactor isolation is installed near the ground level, the height of the water source seen from the pump is It is possible to secure NPSH even if the pump is installed above the water level of the suppression pool.

Therefore, in this embodiment, the reactor isolation cooling system steam turbine 26, the pump, the drain pot 24, and the steam trap 31 are installed at a level above the suppression pool water level, and the drain line 30 is installed.
Guides to the suppression pool 33 with a continuous downward gradient and submerges the tip.

(1) The operating method is as follows.

A). Draining water after leakage test of main steam isolation valve For draining water after leakage test of main steam isolation valve, the valve 59 is opened and the water is discharged to the suppression pool 33.

B). The reactor deaeration operation is performed by opening the main steam drain line valves 11, 12, 15, and 60, closing the suppression pool side valve 59, and further opening the U seal inlet valves 104 and 105. The U seal 107 allows the drain cooler 100 and the drain transfer line 102.
Since the drain is drained from the drain, the deaeration line is not blocked by the drain. As a result, the reactor 1 and the main condenser 8 are connected to each other through the main steam line 2, the main steam drain line 10, the drain cooler 100, and the drain transfer line 102 without causing blockage due to a drain pool in the middle, The reactor 1 is degassed by the vacuum of the main condenser 8. The drain discharged from the U seals 107 and 108 is
Collect in drain sump.

C). When the reactor deaeration operation is completed during the reactor nuclear heating to the plant normal operation, the U-seal inlet valves 104 and 105 are closed before the reactor nuclear heating is started. Main steam drain line 1 after starting nuclear reactor heating
The drain flowing into the drain cooler 100 from 0 and 16 is
Here, the whole amount is condensed and collected in the main condenser 8.

(2) Regarding interlock, a). When the pressure gauge 81 detects an abnormally high drain cooler pressure, the drain cooler inlet valve 60 is automatically closed.

B). When the U-seal thermometer 106 detects an abnormally high temperature, the U-seal inlet valves 104, 10 are automatically
Close 5

(3) To prevent vacuum breakage of the main condenser, the U-seal 107 used during deaeration of the reactor should have a height of 10 m or more, and the space between the vacuum main condenser 8 and the atmosphere open side of the U-seal. Seal completely.

As described above with reference to various examples, in this drain processing apparatus, the suppression chamber and the flash tank or the drain cooler are provided at a position relatively lower than the main steam line, and the flash is also provided. Between the tank or drain cooler and the main condenser, there is a condensation drain line that guides the condensed water in the flash tank to the main condenser, so the steam drain is collected in the main condenser. Therefore, the main steam drain and the reactor isolation cooling system drain can be properly recovered even in a deep reactor plant in which the reactor is located several tens of meters below the main condenser. .

[0107]

As described above, according to the present invention, even if the installation height of the main steam line is relative to the main condenser, hammering by gas-liquid two-phase flow is performed. It is possible to obtain a reactor steam condensation drain processing device of this type capable of processing the main steam drain or the reactor isolation cooling system drain without causing the above.

[Brief description of drawings]

FIG. 1 is a system diagram (state during normal plant operation) showing an embodiment of a reactor vapor condensation drain treatment device of the present invention.

FIG. 2 is a system diagram (a state of water draining operation after a main steam isolation valve leakage test) showing an embodiment of a reactor steam condensation drain treatment device of the present invention.

FIG. 3 is a system diagram (state of reactor deaeration operation) showing an embodiment of a reactor vapor condensation drain treatment device of the present invention.

FIG. 4 is a system diagram (a state at the initial stage of nuclear heating of a nuclear reactor) showing an embodiment of a reactor vapor condensation drain treatment device of the present invention.

FIG. 5 is a system diagram (state during normal plant operation) showing another embodiment of the reactor vapor condensation drain treatment device of the present invention.

FIG. 6 is a system diagram (state during normal plant operation) showing still another embodiment of the nuclear reactor vapor condensation drain treatment device of the present invention.

FIG. 7 is a system diagram (state during normal plant operation) showing still another embodiment of the nuclear reactor vapor condensation drain treatment device of the present invention.

FIG. 8 is a system diagram (state during normal plant operation) showing still another embodiment of the nuclear reactor vapor condensation drain treatment device of the present invention.

[Explanation of symbols]

1 ... Reactor, 2 ... Main steam line (inside the reactor containment vessel), 3 ... Main steam isolation valve (inside the reactor containment vessel), 4 ...
Main steam isolation valve (outside of PCV), 5 ... Main steam line (outside of PCV), 6 ... Main turbine shutoff valve, 7
... turbine, 8 ... main condenser, 9 ... turbine bypass valve,
10 ... Main steam drain line (inside the PCV), 1
4 ... Flow rate limiting orifice, 16 ... Main steam drain line (outside of containment vessel), 18 ... Flow rate limiting orifice,
23 ... Reactor isolation cooling system turbine drive steam supply line, 24 ... Drain pot, 26 ... Reactor isolation cooling system turbine, 29 ... Reactor isolation cooling system turbine exhaust line, 30 ... Reactor isolation cooling system drain Line, 31 ... Steam trap, 32 ... Reactor containment vessel, 33 ... Suppression chamber (water holding part is also called suppression pool), 34 ... Liquid waste treatment facility, 50 ... Flash tank, 52 ... Water level gauge, 54 ... Drain Transfer pump, 8
0 ... Control valve (flash tank pressure control valve), 81 ... Pressure gauge, 82 ... Control valve (flash tank water level control valve),
83 ... Safety valve, 71 ... Steam condenser, 73 ... Cooling water line, 90 ... Water level gauge, 91 ... Thermometer, 92 ... Steam trap, 93 ... Steam trap, 94 ... Control device, 95
... turbine bypass small valve, 98 ... check valve (vacuum breaking valve), 100 ... drain cooler, 101 ... cooling water line,
106 ... Thermometer, 107 ... U seal.

 ────────────────────────────────────────────────── ─── Continuing from the front page (72) Inventor Takashi Asano 3-2-1, Sachimachi, Hitachi City, Ibaraki Prefecture Within Hitachi Engineering Co., Ltd.

Claims (23)

[Claims] 1. A main steam line for supplying main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line, wherein main condensed liquefied water in the main steam line is provided. Reactor steam condensing drain treatment facility that is designed to discharge and remove steam from the steam line to the main steam drain line, or in addition to the main steam line and main steam drain line, steam generated in the reactor is isolated from the reactor. The reactor isolation cooling system steam line that supplies the cooling turbine drive steam turbine, and the reactor isolation cooling system steam drain line that branch off from this reactor isolation cooling system steam line Condensed liquefied water in the steam line is designed to be discharged and removed from the reactor isolation cooling system steam line to the reactor isolation cooling system steam drain line. In the processing equipment for drain, in the middle of the flow path of the main steam drain line, and in the middle of the flow path of the reactor isolation cooling system steam drain line, an orifice for limiting the discharge amount of drain, or a steam trap, Alternatively, a control valve is provided, and a flash tank is provided at a position relatively lower than the main steam line, and the discharge side end of the main steam drain line or the reactor isolation cooling system steam is provided in the flash tank. The discharge side end of the drain line, or both the discharge side end of the main steam drain line and the discharge side end of the reactor isolation cooling system steam drain line are coupled via a flow path,
The flash tank is configured to separate the main steam drain, the steam separation drain for the reactor cooling system, or both into a vapor phase and a condensed water phase, and the upper part of the flash tank and the main steam turbine for power generation. The condenser is connected from the upper part of the flash tank to the main condenser via a flow path that connects continuously with an upward slope or horizontal slope, and the lower part of the flash tank and the main condenser of the steam turbine for power generation are connected. Or the lower part of the flash tank and the radioactive liquid waste treatment equipment, or the lower part of the flash tank and both the main condenser of the steam turbine for power generation and the radioactive liquid waste treatment equipment are connected via a flow path. Along with this flow path, a pump with the ability to transfer the condensed water in the flash tank to the main condenser or radioactive liquid waste treatment facility. Nuclear steam condensate drainage processing facility characterized by comprising a. 2. The inside of the flash tank is controlled by ON-OFF operation control or rotation speed control of a pump having an ability to transfer condensed water in the flash tank to a main condenser or a radioactive liquid waste treatment facility. 2. The reactor steam condensate drain treatment equipment according to claim 1, further comprising a control device for adjusting the water level of the condensed water of 1. 3. A water level adjusting valve is provided in a discharge side flow path of a pump having an ability to transfer condensed water in the flash tank to a main condenser or a radioactive liquid waste treatment facility, and the water level adjusting valve is provided. The reactor steam condensate drain treatment equipment according to claim 1, further comprising a control device for adjusting the water level of the condensed water in the flash tank by controlling the opening and closing of the. 4. A suppression pool connection line branched from a main steam drain line connecting the main steam line and the flash tank is provided, and its discharge end is led to a suppression pool installed at a position relatively lower than the main steam line, The discharge end is submerged in the suppression pool, and the flash tank inlet and suppression pool connection line of the main steam drain line can be switched by selecting either the flash tank or the suppression pool as the discharge destination of the main steam drain. The nuclear reactor steam condensate drain treatment equipment according to claim 1, wherein the arranged valve is provided. 5. A main steam line for supplying main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line are provided, and main condensed liquefied water in the main steam line is provided. Reactor steam condensing drain treatment facility that is designed to discharge and remove steam from the steam line to the main steam drain line, or in addition to the main steam line and main steam drain line, steam generated in the reactor is isolated from the reactor. The reactor isolation cooling system steam line that supplies the cooling turbine drive steam turbine, and the reactor isolation cooling system steam drain line that branch off from this reactor isolation cooling system steam line Condensed liquefied water in the steam line is designed to be discharged and removed from the reactor isolation cooling system steam line to the reactor isolation cooling system steam drain line. In the processing equipment for drain, in the middle of the flow path of the main steam drain line, and in the middle of the flow path of the reactor isolation cooling system steam drain line, an orifice for limiting the discharge amount of drain, or a steam trap, Alternatively, a control valve is provided, and a flash tank is provided at a position relatively lower than the main steam line, and the discharge side end of the main steam drain line or the reactor isolation cooling system steam is provided in the flash tank. The discharge side end of the drain line, or both the discharge side end of the main steam drain line and the discharge side end of the reactor isolation cooling system steam drain line are coupled via a flow path,
The flash tank is configured to separate the main steam drain, the steam separation drain for the reactor cooling system, or both into a vapor phase and a condensed water phase, and the upper part of the flash tank and the main steam turbine for power generation. The condenser is connected from the upper part of the flash tank toward the main condenser via a flow path that connects continuously with an upward slope or horizontal slope, and a pressure control valve is provided in this flow path to control the pressure. A control device that regulates the pressure inside the flash tank by controlling the opening and closing of the valve is installed, and the lower part of the flash tank and the main condenser of the steam turbine for power generation, or the lower part of the flash tank and the radioactive liquid waste treatment facility. Alternatively, connect the flow path between the bottom of the flash tank and both the main condenser of the steam turbine for power generation and the radioactive liquid waste treatment facility. And a water level control valve in this flow path, and a control device for controlling the water level in the flash tank by controlling the opening and closing of this water level control valve is provided. Processing equipment. 6. A main steam line for supplying the main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line, and main condensed liquefied water in the main steam line is provided. Reactor steam condensing drain treatment facility that is designed to discharge and remove steam from the steam line to the main steam drain line, or in addition to the main steam line and main steam drain line, steam generated in the reactor is isolated from the reactor. The reactor isolation cooling system steam line that supplies the cooling turbine drive steam turbine, and the reactor isolation cooling system steam drain line that branch off from this reactor isolation cooling system steam line Condensed liquefied water in the steam line is designed to be discharged and removed from the reactor isolation cooling system steam line to the reactor isolation cooling system steam drain line. In the processing equipment for drain, in the middle of the flow path of the main steam drain line, and in the middle of the flow path of the reactor isolation cooling system steam drain line, an orifice for limiting the discharge amount of drain, or a steam trap, Alternatively, a control valve is provided, and a flash tank is provided at a position relatively lower than the main steam line, and the discharge side end of the main steam drain line or the reactor isolation cooling system steam is provided in the flash tank. The discharge side end of the drain line, or both the discharge side end of the main steam drain line and the discharge side end of the reactor isolation cooling system steam drain line are coupled via a flow path,
The flash tank is configured to separate the main steam drain, the steam separation drain for the reactor cooling system, or both into a vapor phase and a condensed water phase, and the upper part of the flash tank and the main steam turbine for power generation. The condenser is connected from the upper part of the flash tank to the main condenser via a flow path that connects continuously with an upward slope or horizontal slope, and the lower part of the flash tank and the main condenser of the steam turbine for power generation are connected. Or the lower part of the flash tank and the radioactive liquid waste treatment equipment, or the lower part of the flash tank and both the main condenser of the steam turbine for power generation and the radioactive liquid waste treatment equipment are connected via a flow path. The reactor steam condensing drain treatment facility characterized by the above. 7. A drain line is provided in the lower portion of the flash tank or in a flow path connected to the lower portion of the flash tank, and the discharge end portion of the drain line is guided to a drain receiver open to the atmosphere. A U-seal-shaped water-sealing structure or a water-sealing structure in which the drain line discharge end is submerged is provided in the flow path consisting of this drain line and the flow path connecting to the lower part of the tank, and the internal pressure of the flash tank is restored Even if it has the same degree of vacuum as a water container,
7. Condensed water in the flash tank can be discharged through this line without air flowing into the flash tank from this drain line, and a stop valve is provided in this drain line. Reactor steam condensation drain treatment equipment. 8. A main steam line for supplying the main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line, and main condensed liquefied water in the main steam line is provided. Reactor steam condensing drain treatment facility that is designed to discharge and remove steam from the steam line to the main steam drain line, or in addition to the main steam line and main steam drain line, steam generated in the reactor is isolated from the reactor. The reactor isolation cooling system steam line that supplies the cooling turbine drive steam turbine, and the reactor isolation cooling system steam drain line that branch off from this reactor isolation cooling system steam line Condensed liquefied water in the steam line is designed to be discharged and removed from the reactor isolation cooling system steam line to the reactor isolation cooling system steam drain line. In the processing equipment for drain, in the middle of the flow path of the main steam drain line, and in the middle of the flow path of the reactor isolation cooling system steam drain line, an orifice for limiting the discharge amount of drain, or a steam trap, Alternatively, a control valve is provided, and a flash tank is provided at a position relatively lower than the main steam line, and the discharge side end of the main steam drain line or the reactor isolation cooling system steam is provided in the flash tank. The discharge side end of the drain line, or both the discharge side end of the main steam drain line and the discharge side end of the reactor isolation cooling system steam drain line are coupled via a flow path,
The flash tank is configured to separate the main steam drain, the steam separation drain for the reactor cooling system, or both into a vapor phase and a condensed water phase, and the upper part of the flash tank and the main steam turbine for power generation. The condenser is connected from the upper part of the flash tank to the main condenser through a flow path that connects continuously with an upward slope or a horizontal slope, and a drain line is provided at the bottom of the flash tank to discharge it. In addition to guiding the end to a drain receiver open to the atmosphere, this drain line is provided with a U-seal-shaped water seal structure or a water seal structure in which the drain line discharge end is submerged, and the internal pressure of the flash tank is the main condensate. Even if the vacuum level is the same as that of the vessel, the condensed water in the flash tank can be transferred to this line without air flowing into the flash tank from this drain line. As well as configured to be discharged through the reactor vapor condensation drainage treatment facility, characterized in that a stop valve provided in the drain line. 9. A suppression pool connection line branched from a main steam drain line connecting the main steam line and the flash tank is provided, and its discharge end is led to a suppression pool installed at a position relatively lower than the main steam line, The discharge end is submerged in the suppression pool, and the flash tank inlet and suppression pool connection line of the main steam drain line can be switched by selecting either the flash tank or the suppression pool as the discharge destination of the main steam drain. The reactor steam condensate drain treatment equipment according to any one of claims 5 to 8, which is provided with arranged valves. 10. A main steam line for supplying main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line, wherein the condensed liquefied water in the main steam line is mainly contained. Reactor steam condensing drain treatment facility that is designed to discharge and remove steam from the steam line to the main steam drain line, or in addition to the main steam line and main steam drain line, steam generated in the reactor is isolated from the reactor. The reactor isolation cooling system steam line that supplies the cooling turbine drive steam turbine, and the reactor isolation cooling system steam drain line that branch off from this reactor isolation cooling system steam line Condensation liquefied water in the steam line is discharged from the reactor isolation cooling system vapor line to the reactor isolation cooling system vapor drain line and is removed. In the drain treatment facility, in the middle of the flow path of the main steam drain line, and in the middle of the flow path of the reactor isolation cooling system steam drain line, an orifice for limiting the discharge amount of drain, or a steam trap, Alternatively, a control valve is provided, and a flash tank is provided at a position relatively lower than the main steam line, and the discharge side end of the main steam drain line or the reactor isolation cooling system steam is provided in the flash tank. The discharge side end of the drain line, or both the discharge side end of the main steam drain line and the discharge side end of the reactor isolation cooling system steam drain line are coupled via a flow path,
The flash tank is configured to separate the main steam drain, the steam separation drain for the reactor isolation cooling system, or both into a vapor phase and a condensed water phase, and water cooling is performed at a position relatively higher than the flash tank. -Type steam condenser is installed, the upper part of the flash tank is connected to the steam condenser, and a flow path for guiding the vapor and liquid separated vapor in the flash tank to the steam condenser, and the lower part of the steam condenser and the flash tank are connected. A flash tank that is connected via a seal-like water-sealing structure and that guides the condensed water generated in the steam condenser to the flash tank, and the flash tank upper part and the steam condenser upper part and the suppression chamber gas phase part are connected. And a flow path for making the internal pressure of the steam condenser atmospheric pressure, the lower part of the flash tank and the main condenser of the steam turbine for power generation, Connects the lower part of the flash tank and the radioactive liquid waste treatment equipment, or the lower part of the flash tank and both the main condenser and the radioactive liquid waste treatment equipment of the steam turbine for power generation through the flow path. A reactor steam condensate drain treatment facility having a pump capable of transferring condensed water in a flash tank to a main condenser or a radioactive liquid waste treatment facility on this flow path. 11. The inside of the flash tank is controlled by ON-OFF operation control or rotation speed control of a pump having an ability to transfer condensed water in the flash tank to a main condenser or a radioactive liquid waste treatment facility. 11. The reactor steam condensate drain treatment equipment according to claim 10, further comprising a control device that adjusts the water level of the condensed water of 1. 12. A water level control valve is provided in a discharge side flow path of a pump having an ability to transfer condensed water in the flash tank to a main condenser or a radioactive liquid waste treatment facility, and the water level control valve is provided. 11. The nuclear reactor steam condensate drain treatment equipment according to claim 10, further comprising a control device for adjusting the water level of the condensed water in the flash tank by controlling the opening and closing of the. 13. A suppression pool connection line branched from a main steam drain line connecting the main steam line and the flash tank is provided, and its discharge end is led to a suppression pool installed at a position relatively lower than the main steam line, The discharge end is submerged in the suppression pool, and the flash tank inlet and suppression pool connection line of the main steam drain line can be switched by selecting either the flash tank or the suppression pool as the discharge destination of the main steam drain. The reactor steam condensation drain treatment equipment according to any one of claims 10 to 12, which is provided with arranged valves. 14. A main steam line for supplying main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line, wherein condensed liquefied water in the main steam line is mainly contained. In a treatment facility for a reactor steam condensation drain that is formed to be discharged and removed from a steam line to a main steam drain line, in the middle of the flow path of the main steam drain line, an orifice that limits the drain discharge amount, or, A steam trap or a control valve is provided, and a water-cooled drain cooler is provided at a position relatively lower than the main steam line, and the drain side end of the main steam drain line is flowed to the drain cooler. The main vapor drain, which is connected through the channel and flows into the drain cooler in a gas-liquid two-phase flow, is cooled by the drain cooler, where all the vapor phases are condensed into condensed water. Condensed water retention part of drain cooler and main condenser of steam turbine for power generation, condensed water retention part of drain cooler and radioactive liquid waste treatment facility, or condensed water retention of drain cooler A steam condensate drain treatment facility for a nuclear reactor, characterized in that both the main part of the steam turbine for power generation and the radioactive liquid waste treatment facility are connected via a flow path. 15. A control valve for providing a drain cooler with a pressure gauge, a thermometer, or both a pressure gauge and a thermometer, and for controlling the drain discharge amount in the middle of the flow path of the main steam drain line. When the pressure of the drain cooler increases, or when the temperature of the drain cooler rises, the pressure of the drain cooler by operating the control valve in the closing direction,
The reactor steam condensate drain treatment facility according to claim 14, further comprising a controller configured to adjust the temperature. 16. A lower portion of the drain cooler, or
A drain line is provided in the flow path that connects to the condensed water retention part of the drain cooler, and its discharge end is led to the drain receiver that is open to the atmosphere, and connected to this drain line or the condensed water retention part of the drain cooler. The flow path consisting of this flow path and this drain line is provided with a U-seal-shaped water seal structure or a water seal structure in which the drain end of the drain line is submerged, and the internal pressure of the drain cooler is the same as that of the main condenser. Even if the degree of vacuum is
16. The condensed water in the flash tank can be discharged through the line without air flowing into the drain cooler from the drain line, and a stop valve is provided in the drain line. Reactor vapor condensation drain treatment facility described. 17. A suppression pool connection line branched from the main steam drain line connecting the main steam line and the drain cooler is provided, and its discharge end is guided to a suppression pool installed at a position relatively lower than the main steam line. , The discharge end is submerged in the suppression pool, and the drain cooler inlet or the suppression pool connection line of the main steam drain line is selected and switched between the drain cooler and the suppression pool as the main steam drain discharge destination. 17. The reactor steam condensate drain treatment equipment according to any one of claims 14 to 16, wherein a valve arranged so as to be provided is provided. 18. A main steam line for supplying main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line, wherein main condensed liquefied water in the main steam line is provided. In a treatment facility for a reactor steam condensation drain that is formed to be discharged and removed from a steam line to a main steam drain line, in the middle of the flow path of the main steam drain line, an orifice that limits the drain discharge amount, or, A steam trap or a control valve is provided, and a suppression pool is provided at a position relatively lower than the main steam line, and the discharge side end of the main steam drain line is connected to this suppression pool via a flow path. , A reactor steam condensation drain treatment facility, characterized in that its discharge end is submerged in a suppression pool. 19. A vacuum break valve or a small hole is provided in the non-submerged part of the main steam drain line, and when the main steam drain line becomes negative pressure, the vacuum break valve or the small hole opens the inside of the suppression chamber. The reactor steam condensation drain treatment equipment according to claim 18, wherein the gas in the gas phase portion is configured to flow into the main steam drain line. 20. A reactor isolation cooling system steam line for supplying steam generated in a reactor to a reactor isolation cooling system driving steam turbine, and a reactor isolation device branched from this reactor isolation cooling system steam line. It is equipped with an intercooling system steam drain line, and is designed to discharge condensed liquefied water in the reactor isolation cooling system steam line from the reactor isolation cooling system steam line to the reactor isolation cooling system steam drain line. In the reactor steam condensate drain treatment facility that exists, in the middle of the flow path of the reactor isolation cooling system steam drain line, an orifice that limits the drain discharge amount, or
A steam trap or a control valve was provided, and the discharge side end of the reactor isolation cooling system steam drain line was connected to the suppression pool via a flow path, and the discharge side end was submerged in the suppression pool. Reactor vapor condensation drain treatment facility characterized by the following. 21. A vacuum break valve or a small hole is provided at a non-submerged portion of the steam drain line for cooling the reactor isolation system so that a vacuum is generated when the steam drain line for the reactor isolation cooling system has a negative pressure. 21. The nuclear reactor steam condensate drain treatment equipment according to claim 20, wherein the gas in the vapor phase portion in the suppression chamber is made to flow into the steam drain line for the reactor isolation cooling system through the break valve or the small hole. 22. Monitoring the suppression pool water temperature,
The reactor steam condensing drain treatment equipment according to any one of claims 18 to 21, further comprising: measurement control equipment that detects a high temperature and automatically starts a suppression pool cooling mode of a residual heat removal system. 23. A main steam line for supplying main steam generated in a nuclear reactor to a steam turbine for power generation, and a main steam drain line branched from this main steam line are provided, and main condensed liquefied water in the main steam line is provided. A treatment facility for a reactor steam condensation drain that is formed to be discharged and removed from a steam line to a main steam drain line, and a turbine bypass line that connects the main steam line and a main condenser of a steam turbine for power generation, Equipment that is equipped with a turbine bypass valve that opens and closes this turbine bypass line, and in which the height of the lowest part of the main steam line is lower than the height of the main condenser, it is higher than the main condenser of the main steam line. Higher than the main condenser upstream of the main condenser of the steam turbine for power generation and the steam turbine for power generation, or the turbine bypass line branched from the main steam line. Of the reactor and the main condenser of the steam turbine for power generation, a reactor degassing line is provided, and a reactor degassing line stop valve is provided on this reactor degassing line to degas the reactor when the reactor starts. By opening the reactor degassing line stop valve during operation, it is possible to degas the non-condensable gas dissolved in the reactor cooling water by connecting the vacuum main condenser and the reactor. In order to discharge the condensed drain generated in the main steam line during the degassing of the reactor from the main steam drain line, the discharge side end of the flash tank, the drain cooler, and the suppression pool are formed. 23. The nuclear reactor steam condensation drain treatment equipment according to any one of claims 1 to 22, which is connected to at least one of the above.