JPS60168507A - Purification apparatus - Google Patents

Abstract

PURPOSE:To well improve the quality of water in a pressure suppression chamber, by reducing the carry-in amount of clad into the pressure suppression chamber. CONSTITUTION:A filter chamber 44 is demarcated in a casing 25 by a cover plate 33 and a support plate 40, and a suction port 30 is confronted to said filter chamber 44. Cylindrical cartridge filters 45 are received in the above mentioned filter chamber 44 and held between the cover plate 33 and the support plate 40. Because water introduced into the casing 25 from a suction pipe 9A is withdrawn to an emitting pipe 9B through the opening 42 of the support plate 40, clad is removed by the above mentioned filters 45. Therefore, if the purification apparatus 20 of water in a pressure suppression chamber is provided to the cooling system of a nuclear reactor, the carry-in amount of clad to the pressure suppression chamber is reduced to a large extent and, by the reduction of radioactive clads, the reduction in exposure is achieved at the time of the maintenance of the suppression chamber and peripheral machineries.

Description

DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a purification device for purifying fluid, and particularly to a purification device suitable for improving the water quality of a pressure suppression chamber in nuclear power generation equipment.

[Technical background of the invention and its problems]

In nuclear power generation facilities, a reactor cooling system that uses water in a pressure suppression chamber as a water source has conventionally been configured as shown in FIG.

In FIG. 1, a strainer 2 is housed in a pressure suppression chamber 1, and a pump 4 is interposed in a suction line 3 connected to the strainer 2.

Further, the discharge line 15 of this pump 4 is the inflow line 6'f
: It is connected to the reactor containment vessel 7 and the reactor pressure vessel 8 through the reactor vessel 7, and the water in the pressure suppression chamber 1 is injected into both vessels 7 and 8. Further, a test line 9 for circulating water from the discharge line 5 into the pressure suppression chamber 1
The test line 9 is branched, and an on-off valve 10 is interposed in the test line 9.

The pressure suppression chamber water 11J of the pressure suppression chamber 1 is injected into the reactor pressure vessel 8 by the reactor cooling system pump 4 in an emergency. Function check, check the health of the suction line 3 from the pressure suppression chamber 1, check the health of the line from the discharge line 5 to the middle of the injection 2-in-6, and interlock the opening and closing of the minimum flow valve to the pressure suppression chamber 1. Used as confirmation.

In order to maintain the integrity of the emergency core cooling system, during normal operation of nuclear power generation facilities, the reactor containment vessel 7
The injection line 6 which is injected into the reactor pressure trough 8
is in a standby state, and uses the pressure suppression chamber water 11 as a water source, the strainer 2 built in the pressure suppression chamber 1 and the suction line 3 watertightly connected to the pressure suppression chamber 1, and the discharge line 5 of the pump 4. The test line 9 must be operated with a line that recirculates the suppression chamber 1, and the health of the pump 4 and the system must be checked once a month, and the health must also be checked during periodic inspections. . Therefore, during test operations during normal plant operation, the suction line 3, pump 4, discharge line 5, injection line 6, and test line 9 are sealed with water, and water containing crud due to corrosion of the inner walls of the pipes is The crud is returned to the pressure suppression chamber 1 and accumulates in the pressure suppression chamber 1. Next, if the pressure suppression chamber water 11 is injected into the reactor pressure vessel 8 by the pump 4 during a reactor accident as a water source, it will damage the integrity of the reactor internal structure and cause activation of the crud in the ordered water. Further increasing the exposure dose is not desirable in terms of reducing exposure. Further, the residual heat removal system is used to shut down a nuclear power plant, and reactor water is flowed into the piping, and the system is kept in a normal standby state and is sealed with water containing activated crud. In the residual heat removal system, the pump 4 is periodically driven during test operation, and water containing activated crud flows into the pressure suppression chamber 1. This increases the radiation dose in the pressure suppression chamber 1 and requires considerable effort and labor during maintenance. Therefore, in order to reduce exposure, it becomes necessary to improve the quality of the pressure suppression chamber water 11.

[Purpose of the invention]

In view of the above-mentioned points, an object of the present invention is to provide a purification device that can reduce the amount of crud brought into the pressure suppression chamber and improve the quality of water in the pressure suppression chamber.

[Summary of the invention]

In order to achieve the above-mentioned object, a purification device according to the present invention includes a casing having an opening on the - side, a cover plate detachably attached so as to cover the opening of the casing, and the cover plate. a plurality of support shafts protruding into the casing from the support plate integrally supported by the cover plate; and defined by the cover plate and the support plate;
It has a filtration chamber facing the suction port, and a plurality of cartridge filters housed within the filtration chamber, and the inside of the cartridge filter is communicated with the discharge port.

[Embodiments of the invention]

The present invention will be explained below with reference to embodiments shown in the drawings. Note that the same components as those of the conventional device described above are denoted by the same reference numerals in the drawings, and the explanation thereof will be omitted.

FIG. 2 shows a reactor cooling system in which a purifier hole of the present invention is installed in a test line 9, and an inlet electric valve 21 is installed in the test line 9 on the upstream side of the purifier hole. There is. In addition, a pino line n that connects these inlet electric valves 21 and purifier holes is provided in the test line 9, and this pino line 221C
A pi-no-zo-sumi valve is installed. Further, a test line motor-operated valve U is interposed in the test line 9 upstream of the connection portion of the bypass line n.

The purifier hole has a cylindrical casing 25 having an upper opening 26 as shown in FIGS.
There are 8 surrounding areas. A suction pipe 9A is attached to the center of the bottom wall of the casing.
The suction port opening faces into the casing /25. A flange 31 is provided around the outer peripheral surface of the suction pipe 9A in the casing δ, and an annular flange 32 is provided around the inner peripheral surface of the peripheral wall n on the same horizontal plane as the flange 31. Further, a discharge pipe 9B is connected to the bottom wall 4.

The upper opening 26Fi of the casing 5 is covered with a circular cover plate 33.
is the flange of the casing 5 (each of the plurality of poles) 3
4 and Nara) 35 is removably attached. A plurality of supporting shirts are attached to the peripheral edge of the lower surface of the cover plate (3).
6 are provided to protrude in the circumferential direction, and the lower end of each support shirt 36 reaches close to the bottom wall of the casing 5. In addition, a plurality of guide rods 37 are provided on the lower surface of the cover plate inside these support shafts and protrude in the circumferential direction, and these guide rods 37Ifi are approximately the same length as the support shaft 36. It has a certain quality. A support plate 40 is seated on the flanges 31 and 32 on the inner peripheral surface of the suction pipe 9A and the peripheral wall n of the casing 5 via O-rings 38 and 39i. Center hole 41 for suction pipe 9A and guide rod 37
A large-diameter opening 42 for inserting the support shirt 36 and a small-diameter hole for inserting the support shirt 36 are formed at corresponding positions. By screwing a nut 43 onto the lower end of each support shaft 36, the support plate 40 is integrated with the cover plate. A filtration chamber 44 is defined within the casing δ by these cover plates and the support plate 40, and an inlet port faces the filtration chamber 44. A cylindrical cartridge filter 45 is housed in the filtration chamber 44, and the cartridge filter 45 is held between the cover plate and the support plate 40. A plurality of cartridge filters 45 are arranged on the circumference so as to surround each guide rod 37. Cartridge filter 4
5 is said to have a capacity that can sufficiently remove the generated crud for one year.6 Furthermore, ring-shaped rubber sheaths 46g and 46b as elastic sheets are provided at the vertical intermediate position and at the upper end of each cartridge filter 45. Moreover, the adhesion between the bullet and the cover plate 33 in the vertical direction is made good. Note that a hanging metal fitting 47 is provided on the upper surface of the cover plate 33.
is installed protrudingly. Further, in FIG. 4, the support shaft 36, the guide rod 37, and the cartridge filter 4
5 etc., only one is shown, and the other illustrations are omitted.

According to the above-described configuration, water introduced into the casing 5 from the suction pipe 9A passes from the outer circumferential side to the inner circumferential side of the cartridge filter 45 when passing through the opening 42 of the support plate 40 to the discharge pipe 9B. , cartridge filter 4
5 removes the cladding. Therefore, by providing a purification device for the pressure suppression chamber water 11 in the test line 9, it is possible to check the function of the pump 4 and the integrity of the suction line 3, discharge line 5, and test line 9 during normal operation of the nuclear power generation facility. In order to confirm the
During test operation, an appropriate purification flow rate is set using the electric purifier inlet valve 21 in the test line 9, and the crud in the piping is removed by the purifier in the pressure suppression chamber 1. It is possible to reduce the amount brought into the interior. In addition, the jet flow from the test line 9 lifts up the Clara P accumulated at the bottom of the pressure suppression chamber 1, and the crud is thrown up by the purification device installed in the test line 9 while the pump 4 is operating. can also be removed. Next, the purifier inlet electric valve 21 of the test line 9 is closed, and the bypass ' that bypasses the purifier 20 is closed.
The electric valve 23 is opened and a test operation of the pump 4 of the emergency core cooling system is performed. By installing the purification device 20 for the pressure suppression chamber water 11 in the reactor cooling system in this way, the amount of Clara r brought into the pressure suppression chamber L can be significantly reduced, and the amount of activated crud can be reduced. Radiation exposure can be reduced during maintenance of the pressure suppression chamber 1 and maintenance of peripheral equipment.

Furthermore, a synergistic effect is produced in order to improve the health of peripheral equipment that uses the pressure suppression chamber water 11 as a water source. Furthermore, pressure suppression chamber 1
When water is used as a water source and injected into the reactor pressure vessel 8, the amount of water brought into the reactor is reduced, and the integrity of equipment such as reactor internal structures is improved.

On the other hand, the purification device is added to ZEL) 34 and NUT 35.
The cover plate 33 can be separated from the casing 5 by removing the cover plate 33, and the hook of a winch (not shown) is hung on the hanging fitting 47 to lift the cartridge filter 45, thereby making it easy to replace the cartridge filter 45. It can be done in a short time. This replacement work of the cartridge filter 45 is performed at the time of regular inspection once a year depending on the capacity of the cartridge filter 45. The replaced cartridge filter 45 is drum-canned.

FIG. 5 shows the crud capture capacity of 9 per filtration area with respect to the linear flow rate of the filtering portion of the cartridge filter 45.

As an example, once a year cartridge filter 45 is used for the emergency core cooling system of a 1.1 million MWe class nuclear power plant.
Assuming that the cartridge filter 45 is to be replaced, the size of the cartridge filter 45 will be estimated. Assuming that the internal surface area of the carbon steel piping in the emergency core cooling system is approximately 500 mm, the annual corrosion capacity is calculated as follows: Given that the corrosion rate of carbon steel is 100 mdm, the emergency core cooling system is tested once a month. If this is done, 60Ky/year of crud will occur.

Fig. 5 Linear flow rate of cartridge filter 45 1rrL
/h, the required filtration area is 120 from the crud capture capacity per filtration area of 5001i'/mF.
It becomes i.

For example, if the surface area of one cartridge filter 45 is 0.
5. (In this case, 240 cartridge filters are required, and the size of the container for the cartridge filter 45 is approximately 2,300 cm in height x 650 Wt in diameter. This is a size that can be sufficiently arranged even in the current layout.

〔Effect of the invention〕

As described above, the purification device according to the present invention includes a cover plate that is removably attached to cover one side opening of the casing, and a support shaft that protrudes from the cover plate into the casing. a support plate integrally supported by the plate; defined by the cover plate and the support plate;
It has a filtration chamber with an open suction port and a cartridge filter housed within the filtration chamber, and the interior of the cartridge filter is communicated with the discharge port, so that the cartridge filter can be easily replaced. Also,
When this purification device is installed before the pressure suppression chamber on the test line of the emergency core cooling system, most of the crud is removed by the cartridge filter, making it possible to maintain good water quality in the pressure suppression chamber.

Note that the purification device of the present invention can be applied to various equipment other than nuclear power generation equipment.

[Brief explanation of drawings]

Fig. 1 is a pipe diagram showing a conventional emergency core cooling system, Fig. 2 is a pipe diagram showing an emergency core cooling system to which the purification device of the present invention is applied, and Fig. 3 is a purification device according to the present invention. FIG. 4 is a cross-sectional view of FIG. 3, and FIG. 5 is a graph showing the crud capture capacity by the cartridge filter. DESCRIPTION OF SYMBOLS 1... Pressure suppression chamber, 4... Pump, 7... Reactor containment vessel, 8... Reactor pressure vessel, 9... Test line, purification device, 5... Casing, addition...
- Suction port, 33... Cover plate, 36... Support shaft, 40... Support plate, 44... Filtration chamber, 45...
Cartridge filter, 46a. 46b...Rubber sheet. Applicant's agent Hisashi Hatano Diagram 5 filtration phase 1, 4-lid capacity (9/m) Procedural amendment (voluntary) March 22, 1980 Director-General of the Patent Office Kazuo Wakasugi 1. Indication of the case: Patent Application No. 24,507 of 1980 2. Name of the invention Purification device 3. Person making the amendment Patent applicant related to the case (307) Tokyo Shibaura Electric Co., Ltd. (and 1 other person) 7. "Detailed Description of the Invention" column of the specification to be amended. 8. Contents of amendment Change “ordered” in line ν of page 4 of the specification to “note 98
1 correction 6: <8,

Claims (1)

[Claims] 1. A casing having an opening on the negative side, and a cover plate detachably attached to cover the opening of the casing;
A support plate integrally supported by the cover plate by a plurality of support shafts protruding from the cover plate into the casing, and a filtration chamber defined by the cover plate and the support plate and having an opening inlet. and a plurality of cartridge filters housed within the filtration chamber, the interior of the cartridge filter being communicated with a discharge port. 2. The purification device according to claim 1, wherein the support plate is supported in parallel with the cover plate by a plurality of support shafts, and a cartridge filter is sandwiched between the cover plate and the support plate. 3. The purification device according to claim 1, wherein the cartridge filter has a cylindrical shape, and a ring-shaped elastic sheet is interposed in the middle. 4. The purification device according to claim 1, wherein a guide rod of a cartridge filter is provided on the cover plate in a protruding manner.