CN210802988U - Special sampling device of pressurized water reactor nuclear power plant's primary circuit coolant - Google Patents
Special sampling device of pressurized water reactor nuclear power plant's primary circuit coolant Download PDFInfo
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- CN210802988U CN210802988U CN201921464923.7U CN201921464923U CN210802988U CN 210802988 U CN210802988 U CN 210802988U CN 201921464923 U CN201921464923 U CN 201921464923U CN 210802988 U CN210802988 U CN 210802988U
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- way valve
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model provides a special sampling device of pressurized water reactor nuclear power plant's primary circuit coolant, change 3/8 kelly pipe and public head including female head, tee bend, switch two-way valve, 3/8NPT external screw thread. Wherein the female head, the tee joint, the 3/8NPT external thread turning 3/8 bayonet sleeve and the male head are sequentially connected. The other port of the three-way valve is connected with one end of the switch two-way valve. And an 3/8 stainless steel pipe is arranged at the water outlet of the switch two-way valve and is used for sampling. The utility model discloses can improve chemical sampling analysis efficiency, the sample representativeness is good, realizes the function of the real-time sample of a return circuit coolant.
Description
Technical Field
The utility model belongs to the technical field of the coolant sample, concretely relates to special sampling device of a pressurized water reactor nuclear power plant return circuit coolant.
Background
A pressurized water reactor nuclear power plant REN a loop nuclear sampling system design has two a loop sampling pipeline, and the sampling point sets up at reactor coolant 2 and No. 3 loop hot sections: upstream of the 002GV second steam generator and the 003GV third steam generator, when the reactor coolant pump is operating, the chemical properties in the reactor coolant loop are identical, and a sample taken from one loop can be a true representation of the chemical properties of the entire reactor coolant.
During normal power operation, according to the requirements of the chemical and radiochemical specifications, the boron concentration of the primary loop needs to be continuously monitored by using an online boron meter, and meanwhile, the boron concentration needs to be manually analyzed once a day and compared with the online boron meter. In general, an online boron meter needs to be connected to any sampling pipeline in the hot section of the loop 2 or 3 to meet the requirement of continuous monitoring, so that another sampling pipeline used as redundancy needs to be opened for daily manual sampling, and the sampling is performed according to the method, so that the following defects exist:
1. increased radiation risk: according to the related management requirements of chemical sampling, when sampling is carried out, the dead volume of 3 times of the sample amount in a pipeline needs to be discharged, a sampling pipeline is opened again for liquid discharge, a large amount of high-radioactivity samples are discharged through a glove box, and when a person samples through the glove box, the irradiated risk is increased;
2. the sampling analysis efficiency is low: when a sampling pipeline is opened again, 4 valves on the pipeline need to be opened, wherein 2 valves need to be informed to a main control room by a telephone for matching, a special metal hose for sampling is additionally connected, and the whole sampling operation process is long in time consumption and low in efficiency;
3. the leakage amount of the primary loop coolant is increased, the radioactive waste liquid is increased, and the nuclear safety risk and the operation cost are increased.
Therefore, it is desirable to design a sampling device dedicated to coolant to solve the above-mentioned deficiencies in the prior art.
Disclosure of Invention
The utility model aims at providing a special sampling device of a circuit coolant of pressurized water reactor nuclear power plant improves chemical sampling analysis efficiency, realizes the function of a circuit coolant real-time sample.
The utility model adopts the technical proposal that:
a special sampling device for primary circuit coolant of a pressurized water reactor nuclear power plant comprises a female head, a three-way valve, a two-way switch valve, an 3/8NPT external thread-to-3/8 bayonet sleeve and a male head. Wherein the female head, the tee joint, the 3/8NPT external thread turning 3/8 bayonet sleeve and the male head are sequentially connected. The other port of the three-way valve is connected with one end of the switch two-way valve.
The female head is provided with a clamping sleeve end, and the tee joint is provided with a left port, a right port and an upper port; the switch two-way valve is provided with a water inlet and a water outlet; 3/8NPT external thread-to-3/8 cutting sleeve is provided with a cutting sleeve end and an external thread end;
the ferrule end of the female head is connected with the left port of the tee by using 3/8 stainless steel tube.
The cutting sleeve end of the 3/8NPT external thread turning 3/8 cutting sleeve is connected with the right port of the tee joint through a 3/8 stainless steel pipe.
The male head is in threaded connection with the external thread end of the 3/8NPT external thread turning 3/8 bayonet sleeve.
The water inlet of the switch two-way valve is connected with the upper side port of the tee joint through an 3/8 stainless steel pipe.
And an 3/8 stainless steel pipe is arranged at the water outlet of the switch two-way valve and is used for sampling.
The utility model discloses the beneficial effect who gains does:
1) the function of sampling the coolant of the loop on the online loop of the boron meter in real time is realized, and the sampling representativeness is good;
2) the flow can be effectively controlled, and the sampling can be conveniently performed by chemical personnel;
3) after the special sampling device for the primary circuit coolant of the pressurized water reactor nuclear power plant is accessed into the system, the water sample of the primary circuit keeps flow of 150-;
4) in the implementation sampling process, the amount of radioactive waste liquid is reduced, open redundant pipeline sampling, need to keep about 100L/h sample flow flowing back 10min, the waste liquid amount is about 16.7L, use three-way sampling device to sample, the waste liquid amount is about 0.2L, can reduce 16.5L radioactive waste liquid every time the sample is got after reforming transform promptly, according to the minimum frequency that a unit took the sample once a day, the radioactive waste liquid amount that reduces every year is 6022L, add medicines such as nuclear level lithium hydrate, boron in the water sample of a loop, add a series of processes such as processing, the emission of radioactive waste liquid, can save 10 ten thousand yuan of chemical medicine and radioactive waste liquid treatment cost at least every year.
Drawings
Fig. 1 is a schematic structural diagram of a special sampling device for a primary circuit coolant of a pressurized water reactor nuclear power plant.
Wherein: 1 is a female head; 2 is a tee joint; 3, switching a two-way valve; 4, 3/8NPT external thread turning 3/8 bayonet sleeve; and 5 is a male head.
Detailed Description
The present invention will be described in detail below with reference to the accompanying drawings and specific embodiments.
As shown in fig. 1, the utility model provides a special sampling device of pressurized water reactor nuclear power plant's primary circuit coolant, including female head 1, tee bend 2, switch two-way valve 3, 3/8NPT external screw thread commentaries on classics 3/8 card sleeve pipe 4 and public head 5. Wherein the female head 1, the tee joint 2, the 3/8NPT external thread turning 3/8 bayonet sleeve 4 and the male head 5 are sequentially connected. The other port of the tee joint 2 is connected with one end of a switch two-way valve 3.
The female head 1 is provided with a clamping sleeve end, and the tee joint 2 is provided with a left port, a right port and an upper port; the switch two-way valve 3 is provided with a water inlet and a water outlet; 3/8NPT external thread-turning 3/8 bayonet sleeve 4 is provided with a bayonet sleeve end and an external thread end;
the ferrule end of the female head 1 is connected with the left port of the tee joint 2 by using 3/8 stainless steel tube.
3/8NPT external thread turning 3/8 clamping sleeve pipe 4 clamping sleeve end is connected with the right port of the tee joint 2 through 3/8 stainless steel pipe.
The male head 5 is in threaded connection with the 3/8NPT external thread turning 3/8 external thread end of the bayonet 4.
The water inlet of the two-way valve 3 is connected with the upper port of the tee joint 2 through an 3/8 stainless steel pipe.
The water outlet of the switch two-way valve 3 is provided with an 3/8 stainless steel tube for sampling.
The utility model provides a technical scheme use as follows:
during the normal operation of the unit, the primary loop coolant two-ring sample water returns to the volume control box of the chemical volume control system through the boron meter, the primary loop coolant special sampling device is connected to the downstream of the boron meter flowmeter REN020MD, the male head 5 is directly connected to the system female head REN800WV, the female head 1 is connected with the system female head REN520WV through a metal hose configured by the REN system, other valves on a pipeline are all in an open state, the online boron meter REN012MG keeps 150-hour circulation flow, and manual sampling directly opens the switch two-way valve 3.
The utility model discloses the beneficial effect who gains does:
1) the function of sampling the coolant of the loop on the online loop of the boron meter in real time is realized, and the sampling representativeness is good;
2) the flow can be effectively controlled, and the sampling can be conveniently performed by chemical personnel;
3) after the special sampling device for the primary circuit coolant of the pressurized water reactor nuclear power plant is accessed into the system, the water sample of the primary circuit keeps flow of 150-;
4) in the implementation sampling process, the amount of radioactive waste liquid is reduced, open redundant pipeline sampling, need to keep about 100L/h sample flow flowing back 10min, the waste liquid amount is about 16.7L, use three-way sampling device to sample, the waste liquid amount is about 0.2L, can reduce 16.5L radioactive waste liquid every time the sample is got after reforming transform promptly, according to the minimum frequency that a unit took the sample once a day, the radioactive waste liquid amount that reduces every year is 6022L, add medicines such as nuclear level lithium hydrate, boron in the water sample of a loop, add a series of processes such as processing, the emission of radioactive waste liquid, can save 10 ten thousand yuan of chemical medicine and radioactive waste liquid treatment cost at least every year.
Claims (7)
1. The utility model provides a special sampling device of pressurized water reactor nuclear power plant's primary circuit coolant which characterized in that: the three-way switch comprises a female head (1), a three-way valve (2), a switch two-way valve (3), an 3/8NPT external thread turning 3/8 bayonet tube (4) and a male head (5), wherein the female head (1), the three-way valve (2), the 3/8NPT external thread turning 3/8 bayonet tube (4) and the male head (5) are sequentially connected, and the other port of the three-way valve (2) is connected with the switch two-way valve (3).
2. The special sampling device for primary circuit coolant of pressurized water reactor nuclear power plant as claimed in claim 1, characterized in that: the female head (1) is provided with a clamping sleeve end; the tee joint (2) is provided with a left port, a right port and an upper port; the switch two-way valve (3) is provided with a water inlet and a water outlet; 3/8NPT external thread turning 3/8 bayonet sleeve (4) is provided with a bayonet sleeve end and an external thread end.
3. The special sampling device for primary circuit coolant of pressurized water reactor nuclear power plant as claimed in claim 2, characterized in that: the clamping sleeve end of the female head (1) is connected with the left port of the tee joint (2) through an 3/8 stainless steel tube.
4. The special sampling device for primary circuit coolant of pressurized water reactor nuclear power plant as claimed in claim 2, characterized in that: the clamping sleeve end of the 3/8NPT external thread rotary 3/8 clamping sleeve (4) is connected with the right port of the tee joint (2) through a 3/8 stainless steel pipe.
5. The special sampling device for primary circuit coolant of pressurized water reactor nuclear power plant as claimed in claim 2, characterized in that: and the male head (5) is in threaded connection with the external thread end of the 3/8NPT external thread-turning 3/8 bayonet sleeve (4).
6. The special sampling device for primary circuit coolant of pressurized water reactor nuclear power plant as claimed in claim 2, characterized in that: the water inlet of the switch two-way valve (3) is connected with the upper side port of the tee joint (2) through an 3/8 stainless steel pipe.
7. The special sampling device for primary circuit coolant of pressurized water reactor nuclear power plant as claimed in claim 2, characterized in that: and an 3/8 stainless steel pipe is arranged at the water outlet of the switch two-way valve (3).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201921464923.7U CN210802988U (en) | 2019-09-05 | 2019-09-05 | Special sampling device of pressurized water reactor nuclear power plant's primary circuit coolant |
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| CN201921464923.7U CN210802988U (en) | 2019-09-05 | 2019-09-05 | Special sampling device of pressurized water reactor nuclear power plant's primary circuit coolant |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112102975A (en) * | 2020-09-28 | 2020-12-18 | 三门核电有限公司 | Method for measuring total gas content of pressurized water reactor nuclear power loop |
| CN112151199A (en) * | 2020-09-28 | 2020-12-29 | 三门核电有限公司 | Total gas content measuring device of pressurized water reactor nuclear power loop |
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2019
- 2019-09-05 CN CN201921464923.7U patent/CN210802988U/en active Active
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112102975A (en) * | 2020-09-28 | 2020-12-18 | 三门核电有限公司 | Method for measuring total gas content of pressurized water reactor nuclear power loop |
| CN112151199A (en) * | 2020-09-28 | 2020-12-29 | 三门核电有限公司 | Total gas content measuring device of pressurized water reactor nuclear power loop |
| CN112102975B (en) * | 2020-09-28 | 2021-11-26 | 三门核电有限公司 | Method for measuring total gas content of pressurized water reactor nuclear power loop |
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