CN110828004A - Overpressure protection device for high-temperature gas cooled reactor test and use method thereof - Google Patents
Overpressure protection device for high-temperature gas cooled reactor test and use method thereof Download PDFInfo
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- CN110828004A CN110828004A CN201911243448.5A CN201911243448A CN110828004A CN 110828004 A CN110828004 A CN 110828004A CN 201911243448 A CN201911243448 A CN 201911243448A CN 110828004 A CN110828004 A CN 110828004A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
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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 overpressure protection device for the high-temperature gas cooled reactor test comprises a test tool with a special interface, wherein the test tool is installed at the top of a reactor pressure vessel and is respectively connected with a safety valve and a pressure transmitter, an electric isolation valve is installed at the upstream of the joint of the safety valve and the test tool, a measurement signal of the pressure transmitter is transmitted to a controller, the output end of the controller is respectively connected with a pressure source, an air inlet isolation valve and the electric isolation valve, and the pressure source is connected with the reactor pressure vessel through the air inlet isolation valve. The invention ensures the safety of the large metal pressure container in the air pressure test process and prevents equipment damage caused by accidental overpressure.
Description
Technical Field
The invention relates to the technical field of high-pressure test protection of metal pressure vessels, in particular to an overpressure protection device for a high-temperature gas cooled reactor test and a using method thereof.
Background
The nuclear power plant primary circuit pressure vessel is used as a second safety barrier, is important equipment for preventing radioactive effluents from being released to the outside, is large in size and complex in processing technology, and needs to perform strength test on the reactor primary circuit pressure vessel in the stages of delivery of the pressure vessel and cold test of a power station in order to test the manufacturing quality and the installation quality of the pressure vessel. The strength test is divided into a hydraulic pressure test and an air pressure test, and the pressure vessel of the pressurized water reactor and the general pressure vessel adopt the hydraulic pressure test mode to carry out the strength test in consideration of the high risk of the air pressure test.
Different from a pressurized water reactor nuclear power station, the high-temperature gas cooled reactor nuclear power station is a reactor type with helium or carbon dioxide and other inert gases as a coolant, graphite as a moderator and a graphite matrix as a core structure, and the existence of water vapor in a primary circuit is not allowed in the operation process. According to the limiting condition that the part NB-6000 of the ASME BPVC-III-I-NB partial coil can only adopt the air pressure test to replace the hydraulic pressure test, when parts, accessories or systems are not easy to dry, and trace test media are not allowed to remain when the parts, the accessories or the systems are used, the strength test of a high-temperature gas-cooled reactor, particularly a ball bed type high-temperature gas-cooled reactor pressure container can only adopt the air pressure test.
The conditions of high-temperature gas cooled reactor gas pressure tests at home and abroad are different, and the setting of overpressure protection is different accordingly. By comparing the air pressure test technologies of the German THTR reactor and the Qinghua HTR-10 experimental reactor, the German THTR adopts the structural form of prestressed concrete, the air pressure test pressure is 4.4MPa, and an overpressure protection device is not adopted in the air pressure test process. The HTR-10 experimental reactor adopts a metal pressure container, the pressure of a gas pressure test is 3.85MPa, and an overpressure protection device is not adopted in the process of the gas pressure test. And the HTR-PM demonstration engineering adopts a metal pressure container, and the air pressure test is 9 MPa. Because the compressibility of the gas is much greater than that of the water body, the HTR-PM is not designed with an overpressure protection device in the gas pressure test stage because the pressure rise process of the gas pressure test is much slower than that of the water pressure test.
However, the HTR-PM is different from the THTR and the HTR-10 in that the HTR-PM adopts compressed air as an air pressure test medium, and nearly 50 tons of compressed air is needed according to the calculation of the highest test pressure, so that the medium loading is extremely high, the test risk is greatly improved, and the air pressure test is rare at home and abroad. The temperature change in the air pressure test process has a large influence on the pressure change, and an overpressure protection device needs to be considered in the HTR-PM of the air pressure test stage in order to ensure that the pressure container is not damaged in the test process due to the risk of overpressure caused by the change of the test temperature.
Disclosure of Invention
In order to overcome the defects of the prior art, the invention aims to provide an overpressure protection device for a high-temperature gas cooled reactor test and a using method thereof, which ensure the safety of a large metal pressure container in a gas pressure test process and prevent equipment damage caused by accidental overpressure.
In order to achieve the purpose, the invention adopts the technical scheme that:
the overpressure protection device for the high-temperature gas cooled reactor test comprises a test tool 2 with a special interface, which is arranged at the top of a reactor pressure vessel 1, wherein the test tool 2 is respectively connected with a safety valve 4 and a pressure transmitter 5, an electric isolation valve 3 is arranged at the upstream of the joint of the safety valve 4 and the test tool 2, a measurement signal of the pressure transmitter 5 is transmitted to a controller 6, the output end of the controller 6 is respectively connected with a pressure source 7, an air inlet isolation valve 8 and the electric isolation valve 3, and the pressure source 7 is connected with the reactor pressure vessel 1 through the air inlet isolation valve 8.
The test tool 2 is provided with an exhaust through hole and an instrument interface, the exhaust through hole is connected with the safety valve 4, and the instrument interface is connected with the pressure transmitter 5.
The test tool 2 is connected with a manhole or other flange interfaces of the pressure vessel 1 through a flange.
The test tool 2 is connected with the isolation valve 3 and the pressure transmitter 5 in a welding mode.
The isolation valve 3 is connected with the safety valve 4 through a flange.
The special interface is a container flange blind plate butt joint process interface of the safety valve 4 and the reactor pressure container 1, the two ends of the safety valve are welded through the short pipe butt joint test tool 2, the flange blind plate side is provided with a safety valve exhaust connecting pipe in a socket welding mode or a build-up welding mode, the safety valve end seat flange is welded on one section of the safety valve 4, and the connecting pipe welded through the end seat flange is connected with the safety valve flange in a sealing mode.
The controller 6 is a control system, generally in the form of an industrial personal computer or a centralized control system (DCS), and has the main function of acquiring data signals, issuing control instructions through compiled internal control logic, realizing an automatic closed-loop feedback control function, and manually inputting control instructions to deal with special conditions.
A use method of an overpressure protection device for a high-temperature gas cooled reactor test comprises the following steps:
when a reactor carries out an air pressure test, a test tool 2 is connected with a manhole or other flange interfaces of a pressure vessel 1, namely, the butt joint of a device and the pressure vessel is completed, an interlocking closing fixed value and an opening condition of an isolation valve 3 are set in a controller 6, an interlocking closing fixed value of a pressure source 7 and an air inlet isolation valve 8 is set, system pressure is transmitted to the controller 6 through a pressure transmitter 5, the real-time pressure of the system is compared with set protection pressure in the controller 6, when the system pressure exceeds the protection fixed value of a compressor 7 and the air inlet isolation valve 8, the controller 6 sends a signal instruction to interlock and cut off a power supply of the pressure source 7, the air inlet isolation valve 8 is interlocked and closed to isolate the system from the pressure source, if the system pressure is still increased after the pressure source is isolated, after the protection fixed value preset by a safety valve 4 is reached, the safety valve 4 is opened, and, protecting the pressure vessel and the system from the risk of overpressure damage.
The invention has the beneficial effects that:
in the overpressure protection stage, the main path of system pressure boosting is cut off through logic control, system overpressure caused by external factors is eliminated before the safety valve jumps, the accident of the safety valve jumping is reduced, and internal pressure fluctuation of a container caused by the jumping and pressure relief of the safety valve is prevented.
In the pressure maintaining and leakage detecting stage, the electric isolating valve in front of the safety valve is controlled to be closed, so that the possibility of external leakage caused by internal leakage of the safety valve in overpressure protection can be effectively reduced.
The overpressure protection device has the advantages of simple structure, easy operation in engineering and low manufacturing cost, can effectively prevent container overpressure, and can ensure that no extra leakage point is added in the airtight test process. The method is the best solution for overpressure protection of a large metal pressure vessel, particularly a primary circuit pressure vessel of a high-temperature gas cooled reactor in a gas pressure test.
The overpressure protection device is directly arranged on the reactor pressure vessel, so that the existing interface of the pressure vessel can be effectively utilized, the pipeline on-way pressure loss generated by the connection of the safety valve and a system can be effectively reduced, and the safety valve can realize the overpressure protection function more quickly and accurately.
The safety valve is directly arranged at the top of the pressure container and is used for preventing the pressure container from being over-pressurized; in the air pressure test, the pressure relief speed is low, the safety valve is directly connected with a nozzle at the upper part of the pressure container, and the on-way pressure loss of the pipeline is effectively reduced, so that the requirements of protecting the container and the system in an overpressure protection stage are met.
In consideration of the influence of the safety valve sealing on the system leakage rate, the invention adopts a method of blocking the safety valve by stages, and the safety valve is isolated by the control system at the air tightness test stage, so that the situation that the total leakage rate of the system is increased due to the safety valve leakage in the air tightness pressure test process is prevented.
Drawings
FIG. 1 is a schematic view of the structure of the present invention.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings.
As shown in fig. 1: the system gas pressure test provides compressed gas to be injected into the pressure container 1 through a pressure source 7, an air inlet isolation valve 8 and the like.
According to the requirement of the ASME BPVC-III-I-NB partial volume NB-7000 "the piping on-way pressure loss generated by the connection between the system and the safety valve 4 should not be more than 3% of the relief pressure", so the safety valve 4 is directly mounted on the pressure vessel body. In order to realize the installation of the pressure transmitter 5 and the safety valve 4 without changing the design structure of the original pressure vessel, the connecting tool 2 is installed at a manhole or other flange interfaces of the pressure vessel 1 in a flange mode.
The connecting tool 2 is provided with a safety valve 4 connecting through hole and a pressure transmitter 5 connecting through hole.
An electric isolating valve 3 is arranged in front of the safety valve 4, and the connecting tool 2 is connected with the isolating valve 3 and the pressure transmitter 5 in a welding mode.
The isolating valve 3 and the safety valve 4 are installed in a flange connection mode, and regular verification of the safety valve 4 is facilitated.
The signal of the pressure transmitter 5 is transmitted to the controller 6, and the isolation valve 3, the pressure source 7 and the air inlet isolation valve 8 are automatically controlled through temporary control logic.
The reactor pressure vessel 1 is provided with a test tool 2 with a special interface, the tool 2 is provided with an exhaust through hole for connecting a safety valve 4 and an instrument interface for connecting a pressure transmitter 5, the upper stream of the safety valve 4 is provided with an electric isolating valve 3, a measurement signal of the pressure transmitter 5 is transmitted to a controller 6 (a power station can adopt DCS, and other types can adopt the combined configuration of an industrial personal computer and a data collector), and the controller 6 is added with a temporary control logic for controlling a pressure source 7, an air inlet isolating valve 8 and the temporary electric isolating valve 3.
The invention adds the electric isolation valve 3 in front of the safety valve on the basis of the traditional safety valve 4, and the electric isolation valve 3 is controlled to be closed in the air tightness test stage through logic so as to prevent the influence of the leakage of the safety valve on the total leakage rate of the system, and the electric isolation valve 3 is kept in a normally open state in the strength test stage to communicate the safety valve 4 with the equipment 1, thereby realizing the overpressure protection function. The air inlet isolation valve 8 is automatically cut off under the logic control compiled by the controller 6 at the initial stage of overpressure, the pressure source 7 is interlocked and stopped, and the overpressure caused by external introduction in the pressure range from the initial stage of overpressure to the jump-off of the safety valve 4 is blocked, so that the adverse effect of releasing part of test media after the jump-off of the safety valve 4 on the system pressure is prevented. If the pressure still rises after the system is isolated, the test medium is released through the safety valve 4 to protect the system equipment.
The difference between the logic protection pressure fixed value and the safety valve take-off fixed value set by the interlock close-stop air inlet isolation valve 8 and the cut-off pressure source 7 needs to fully consider the influence of temperature change on system pressure fluctuation, and the safety valve 4 is prevented from taking off due to the system pressure change. Taking HTR — PM as an example, the maximum test pressure of the pressure test is 9.0MPa, the protection signals of the interlock cut-off intake valve 8 and the shut-off pressure source 7 are recommended to be 9.2MPa, and the take-off pressure of the relief valve 4 is recommended to be 9.7MPa (the pressure vessel delivery hydraulic test pressure is 10 MPa).
The working principle of the invention is as follows:
firstly, connecting an overpressure protection device according to a diagram, setting an interlocking closing fixed value and an opening condition of an isolation valve 3 in a controller 6, setting an interlocking closing fixed value of a pressure source 7 and an air inlet isolation valve 8, transmitting system pressure to the controller 6 through a pressure transmitter 5, comparing system real-time pressure with set protection pressure in the controller 6, sending a signal instruction by the controller 6 to interlockingly cut off a power supply of the pressure source 7 when the system pressure exceeds the protection fixed value of the compressor 7 and the air inlet isolation valve 8, interlockingly closing the air inlet isolation valve 8 to isolate the system from the pressure source, if the system pressure is still increased after the pressure source is isolated and reaches a preset protection fixed value of a safety valve 4, opening the safety valve 4, discharging part of system media, and protecting a pressure container and the system from overpressure damage risks.
In order to meet the requirements of the air tightness test, the safety valve 4 is added in the system to be equal to the addition of a known leakage point, so that the electric isolation valve 3 in front of the safety valve 4 needs to be interlocked and closed in order to avoid the influence of the leakage of the safety valve 4 on the overall leakage rate of the system in the air tightness test stage.
The invention can simultaneously realize the requirement of overpressure protection in the strength test of the air pressure test and can also meet the sealing requirement of the air tightness test system.
Claims (8)
1. The overpressure protection device for the high-temperature gas cooled reactor test is characterized by comprising a test tool (2) with a special interface, which is mounted at the top of a reactor pressure vessel (1), wherein the test tool (2) is respectively connected with a safety valve (4) and a pressure transmitter (5), an electric isolation valve (3) is mounted at the upstream of the joint of the safety valve (4) and the test tool (2), a measurement signal of the pressure transmitter (5) is transmitted to a controller (6), the output end of the controller (6) is respectively connected with a pressure source (7), an air inlet isolation valve (8) and the electric isolation valve (3), and the pressure source (7) is connected with the reactor pressure vessel (1) through the air inlet isolation valve (8).
2. The overpressure protection device for the high-temperature gas cooled reactor test according to claim 1, wherein the test fixture (2) is provided with an exhaust through hole and an instrument interface, the exhaust through hole is connected with the safety valve (4), and the instrument interface is connected with the pressure transmitter (5).
3. The overpressure protection device for the high-temperature gas cooled reactor test according to claim 1, wherein the test tool (2) is connected with a manhole or other flange interfaces of the pressure vessel (1) through a flange.
4. The overpressure protection device for the high-temperature gas cooled reactor test according to claim 1, wherein the test fixture (2) is connected with the isolation valve (3) and the pressure transmitter (5) in a welding mode.
5. The overpressure protection device for the high temperature gas cooled reactor test according to claim 1, wherein the isolation valve (3) and the safety valve (4) are connected by a flange.
6. The overpressure protection device for the high-temperature gas-cooled reactor test according to claim 1, wherein the special interface is a butt joint process interface of the safety valve (4) and a vessel flange blind plate of the reactor pressure vessel (1), the two ends of the butt joint test tool (2) are welded through a short pipe, a safety valve exhaust connecting pipe is installed on the flange blind plate side in a socket welding or surfacing welding mode, a safety valve end seat flange is welded on one section of the safety valve (4), and the connecting pipe welded through the end seat flange is connected with the safety valve flange in a sealing mode.
7. The overpressure protection device for the high-temperature gas cooled reactor test according to claim 1, wherein the controller (6) is a control system, such as an industrial personal computer or a centralized control system, and is used for acquiring data signals, issuing control commands through compiled internal control logic, realizing an automatic closed-loop feedback control function, and manually inputting control commands to deal with special situations.
8. The use method of the overpressure protection device for the high-temperature gas cooled reactor test is characterized in that the overpressure protection device comprises a pressure sensor, a pressure sensor and a pressure sensor;
when a reactor carries out an air pressure test, a test tool (2) is connected with a manhole or other flange interfaces of a pressure container (1), namely, the butt joint of a device and the pressure container is completed, an interlocking closing fixed value and an opening condition of an isolation valve (3) are set in a controller (6), an interlocking closing fixed value of a pressure source (7) and an air inlet isolation valve (8) is set, system pressure is transmitted to the controller (6) through a pressure transmitter (5), the real-time pressure of the system is compared with a set protection pressure in the controller (6), when the system pressure exceeds the protection fixed values of a compressor (7) and the air inlet isolation valve (8), the controller (6) sends a signal instruction to interlock and cut off a power supply of the pressure source (7), the air inlet isolation valve (8) is interlocked and closed, the system is isolated from the pressure source, if the system pressure is still raised after the pressure source is isolated, and the protection fixed value preset by a safety valve (4) is reached, the safety valve (4) is opened to discharge part of the system medium, and the pressure container and the system are protected from the risk of overpressure damage.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201911243448.5A CN110828004A (en) | 2019-12-06 | 2019-12-06 | Overpressure protection device for high-temperature gas cooled reactor test and use method thereof |
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| CN201911243448.5A CN110828004A (en) | 2019-12-06 | 2019-12-06 | Overpressure protection device for high-temperature gas cooled reactor test and use method thereof |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112435765A (en) * | 2020-11-23 | 2021-03-02 | 华能山东石岛湾核电有限公司 | High-temperature gas cooled reactor steam generator small-flow cooling system and control method |
| CN113421674A (en) * | 2021-05-26 | 2021-09-21 | 华能山东石岛湾核电有限公司 | Method and device for calculating leakage rate of primary loop during high-temperature reactor cold test |
| CN114220579A (en) * | 2021-10-29 | 2022-03-22 | 华能核能技术研究院有限公司 | Boosting system and method for pressure test before service of primary loop of high-temperature gas cooled reactor |
-
2019
- 2019-12-06 CN CN201911243448.5A patent/CN110828004A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112435765A (en) * | 2020-11-23 | 2021-03-02 | 华能山东石岛湾核电有限公司 | High-temperature gas cooled reactor steam generator small-flow cooling system and control method |
| CN112435765B (en) * | 2020-11-23 | 2022-09-13 | 华能山东石岛湾核电有限公司 | High-temperature gas cooled reactor steam generator small-flow cooling system and control method |
| CN113421674A (en) * | 2021-05-26 | 2021-09-21 | 华能山东石岛湾核电有限公司 | Method and device for calculating leakage rate of primary loop during high-temperature reactor cold test |
| CN114220579A (en) * | 2021-10-29 | 2022-03-22 | 华能核能技术研究院有限公司 | Boosting system and method for pressure test before service of primary loop of high-temperature gas cooled reactor |
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