CN110797129B - Idling test method for shielded main pump of nuclear power plant - Google Patents
Idling test method for shielded main pump of nuclear power plant Download PDFInfo
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- CN110797129B CN110797129B CN201911138647.XA CN201911138647A CN110797129B CN 110797129 B CN110797129 B CN 110797129B CN 201911138647 A CN201911138647 A CN 201911138647A CN 110797129 B CN110797129 B CN 110797129B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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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 invention relates to the technical field of an idling test of a shield main pump of a nuclear power plant, in particular to an idling test method of the shield main pump of the nuclear power plant, which comprises the following steps of L1, installing a temporary instrument and a data acquisition system; l2, performing a hydraulic test on the temporary instrument; l3, starting and shielding the main pump to operate for a period of time, and collecting related test data; l4, stopping the shielded main pump to enable the shielded main pump to enter an idling state, and collecting related test data; l5, shielding the main pump to stop idling; l6, calculating an idling flow curve according to the collected test data; and L7, removing the temporary meter and the data acquisition system. The system adopts eight high-precision temporary differential pressure transmitters and two sets of data acquisition systems to acquire differential pressure data, is high in precision, is very simple and convenient to install and disassemble, acquires temperature, pressure and flow data of a loop through a formal instrument control system of the power plant and a formal instrument of the power plant, and stops the main pump logic pump tripping through the formal main pump bearing water temperature of the power plant, so that the test method is reasonable in design, safe, reliable and simple and convenient to operate.
Description
Technical Field
The invention relates to the technical field of idling tests of a shielding main pump of a nuclear power plant, in particular to an idling test method of the shielding main pump of the nuclear power plant.
Background
The large shielding main pump used for the first-time third-generation nuclear power is a high-rotational-inertia vertical centrifugal pump, and has the idling safety function, and under the accident condition of power loss of a whole plant, the main pump idling provides cooling flow for a reactor core at the initial stage of an accident, so that the serious accident caused by deviation of the reactor core from nucleate boiling is avoided.
After the shielding main pump is installed in a nuclear power plant, a shielding main pump idling test needs to be carried out before a unit manufacturer runs, and the idling performance of the shielding main pump is verified. The shielding main pump idling test has great difference with the shaft seal main pump idling test, the design margin of the shielding main pump idling test is small, the test requirement is high, and the precision and the sampling frequency of formal instruments of a power plant cannot meet the test requirement, so that the shielding main pump idling test method which is reasonable in design, safe, reliable and simple and convenient to operate is required to be provided.
Disclosure of Invention
The invention provides a method for testing the idling of a shielding main pump of a nuclear power plant, aiming at the problems in the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows: a nuclear power plant shield main pump idle running test method comprises the steps of
L1, installing a temporary instrument and a data acquisition system;
l2, performing a hydraulic test on the temporary instrument;
l3, starting and shielding the main pump to operate for a period of time, and collecting related test data;
l4, stopping the shielded main pump to enable the shielded main pump to enter an idling state, and collecting related test data;
l5, shielding the main pump to stop idling;
l6, calculating an idling flow curve according to the collected test data;
l7 removing the temporary meter and data acquisition system.
Preferably, the temporary meter comprises
The cold section 1A temporary differential pressure transmitter is used for being connected with the cold section 1A flow transmitter;
the cold section 1B temporary differential pressure transmitter is used for being connected with the cold section 1B flow transmitter;
the cold section 2A temporary differential pressure transmitter is used for being connected with the cold section 2A flow transmitter;
the cold section 2B temporary differential pressure transmitter is used for being connected with the cold section 2B flow transmitter;
the I-ring hot section temporary differential pressure transmitter 1 is used for being connected with the I-ring hot section flow transmitter A;
the I-ring hot section temporary differential pressure transmitter 2 is used for being connected with the I-ring hot section flow transmitter B;
the II-ring hot section temporary differential pressure transmitter 1 is used for being connected with the II-ring hot section flow transmitter A;
and the II-ring hot section temporary differential pressure transmitter 2 is used for being connected with the II-ring hot section flow transmitter B.
Preferably, the data acquisition system comprises
The first data acquisition system is connected with the cold section 1A temporary differential pressure transmitter, the cold section 1B temporary differential pressure transmitter, the cold section 2A temporary differential pressure transmitter, the cold section 2B temporary differential pressure transmitter, the ring I hot section temporary differential pressure transmitter 1, the ring I hot section temporary differential pressure transmitter 2, the ring II hot section temporary differential pressure transmitter 1 and the ring II hot section temporary differential pressure transmitter 2 and is used for acquiring differential pressure data;
and the second data acquisition system is connected with the main pump circuit breaker and is used for acquiring and shielding the pump stop time of the main pump.
Preferably, the sampling frequency of the first data acquisition system is 10 Hz.
Preferably, the sampling frequency of the second data acquisition system is 1000 Hz.
Preferably, the main pump circuit breaker uses a main pump logic tripping pump of a power plant formal main pump with high idle running water temperature.
Preferably, the flow data of a loop is acquired through a formal instrument control system of the power plant in steps L3 and L4, wherein the formal instrument control system of the power plant is connected with the 1A cold section flow transmitter, the 1B cold section flow transmitter, the 2A cold section flow transmitter, the 2B cold section flow transmitter, the hot section flow transmitter a of the loop i, the hot section flow transmitter B of the loop i, the hot section flow transmitter a of the loop ii, and the hot section flow transmitter B of the loop ii.
Preferably, the temperature and pressure of a primary circuit and the rotating speed, vibration, bearing water temperature, voltage and current data of a shielding main pump are acquired through a formal instrument control system of the power plant at steps L3 and L4.
Preferably, in the step L6, the idling flow curve is calculated by using a normalized flow method according to a relationship that the differential pressure is in direct proportion to a flow square, so as to determine whether the idling performance of the canned main pump meets the acceptance criterion.
Preferably, in step L6, the coasting time constant is calculated by using a time constant method according to a relationship that the pressure difference is proportional to the flow square, so as to determine whether the masked main pump coasting performance meets the acceptance criterion.
Advantageous effects
The shielding main pump idling test method has the advantages that eight high-precision temporary differential pressure transmitters and two sets of data acquisition systems are adopted to acquire differential pressure data, the accuracy is high, the installation and the disassembly are very simple and convenient, the temperature, the pressure and the flow data of a loop are acquired through a power plant formal instrument control system and a power plant formal instrument, and the main pump logic tripping is stopped through the power plant formal main pump bearing water temperature, so that the shielding main pump idling test method is reasonable in design, safe, reliable and simple and convenient to operate.
Drawings
FIG. 1 is a schematic illustration of an installation of a temporary differential pressure transmitter of the present application.
Detailed Description
The technical scheme of the invention is further explained by the specific implementation mode in combination with the attached drawings.
As shown in FIG. 1, the idling test method for the shielded main pump of the nuclear power plant comprises the following steps
And L1, installing a temporary meter and a data acquisition system. The system comprises eight high-precision temporary differential pressure transmitters and two sets of data acquisition systems, wherein 4 of the eight high-precision temporary differential pressure transmitters are cold-section temporary differential pressure transmitters, have the measuring range of 0-0.1379 MPa and the precision of +/-0.1 percent and are connected in parallel with corresponding cold-section flow transmitters; the other 4 are thermal segment temporary differential pressure transmitters with the range of 0-0.345 MPa and the precision of +/-0.1 percent, and are connected with corresponding thermal segment flow transmitters in parallel.
And L2, performing a hydraulic test on the temporary instrument. After the installation is finished, a hydrostatic test is required, and the test pressure adopts the normal operation pressure of a loop to ensure that the pressure of the loop can be borne.
And L3, starting and shielding the main pump to operate for a period of time, and collecting relevant test data.
And L4, stopping the shielded main pump to enable the shielded main pump to enter an idling state, and collecting related test data. A set of data acquisition system acquires parameters of the temporary differential pressure transmitter, and the sampling frequency is 10 Hz; and the other set of data acquisition system acquires a main pump breaker position feedback signal with the sampling frequency of 1000Hz and is used for determining the main pump stop time deviation. The shielding main pump idling test requires that the pump stopping time deviation is not more than 100ms, and the main pump logic pump tripping method is used for stopping the main pump with high formal main pump bearing water temperature in the power plant, meets the requirement of the pump stopping time deviation, does not need to install temporary measures compared with a main pump breaker installation temporary pump stopping switch pump tripping method, and is safer and more efficient.
And L5, shielding the main pump to stop idling.
And L6, calculating an idling flow curve according to the collected test data.
L7 removing the temporary meter and data acquisition system. And (4) after the calculation result is obtained, namely the temporary instrument and the data acquisition system are removed after the test is finished.
The temporary instrument comprises a cold section 1A temporary differential pressure transmitter connected with a cold section 1A flow transmitter, a cold section 1B temporary differential pressure transmitter connected with the cold section 1B flow transmitter, a cold section 2A temporary differential pressure transmitter connected with the cold section 2A flow transmitter, a cold section 2B temporary differential pressure transmitter connected with the cold section 2B flow transmitter, an I-ring hot section temporary differential pressure transmitter 1 connected with the I-ring hot section flow transmitter A, an I-ring hot section temporary differential pressure transmitter 2 connected with the I-ring hot section flow transmitter B, a II-ring hot section temporary differential pressure transmitter 1 connected with the II-ring hot section flow transmitter A and an II-ring hot section temporary differential pressure transmitter 2 connected with the II-ring hot section flow transmitter B.
The cold section 1A flow transmitter, the cold section 1B flow transmitter, the cold section 2A flow transmitter, the cold section 2B flow transmitter, the I-ring hot section flow transmitter A, the I-ring hot section flow transmitter B, the II-ring hot section flow transmitter A and the II-ring hot section flow transmitter B are formal instruments of the power plant, are used in combination with a formal instrument control system of the power plant, and are used for collecting flow data of a loop. The temperature and pressure of a loop and the data of the rotating speed, vibration, bearing water temperature, voltage and current of a shielding main pump can be acquired through a formal instrument control system of the power plant.
The data acquisition system includes first data acquisition system and second data acquisition system, first data acquisition system with cold section 1A interim differential pressure transmitter, cold section 1B interim differential pressure transmitter, cold section 2A interim differential pressure transmitter, cold section 2B interim differential pressure transmitter, I encircle hot section interim differential pressure transmitter 1, I encircle hot section interim differential pressure transmitter 2, II encircle hot section interim differential pressure transmitter 1 and II encircle hot section interim differential pressure transmitter 2 and connect for gather differential pressure data. The sampling frequency of the first data acquisition system is 10 Hz.
And the second data acquisition system is connected with the main pump circuit breaker and is used for acquiring and shielding the pump stop time of the main pump. The sampling frequency of the second data acquisition system is 1000 Hz. The main pump circuit breaker uses the main pump logic pump tripping of the formal main pump bearing water temperature high outage of the power plant.
Before the main pump stops pumping, during idling and after the main pump stops running, differential pressure data are continuously acquired through the data acquisition system, and temperature, pressure and flow data of a loop and parameters of the main pump, such as rotating speed, vibration, bearing water temperature, voltage and current, are acquired through a formal instrument control system of the power plant. The step L6 is specifically to calculate the coasting flow curve by using a normalized flow method according to a relationship that the pressure difference is in direct proportion to the flow square, so as to determine whether the coasting performance of the shielded main pump meets the acceptance criterion. Or calculating the idling time constant by using a time constant method to judge whether the idling performance of the shielding main pump meets the acceptance criterion.
The above-described embodiments are merely illustrative of the preferred embodiments of the present invention and do not limit the spirit and scope of the present invention. Various modifications and improvements of the technical solutions of the present invention may be made by those skilled in the art without departing from the design concept of the present invention, and the technical contents of the present invention are all described in the claims.
Claims (1)
1. A nuclear power plant shielding main pump idling test method is characterized in that: comprises the steps of
L1, installing a temporary instrument and a data acquisition system; the temporary instrument comprises a cold section 1A temporary differential pressure transmitter and is used for being connected with a cold section 1A flow transmitter; the cold section 1B temporary differential pressure transmitter is used for being connected with the cold section 1B flow transmitter; the cold section 2A temporary differential pressure transmitter is used for being connected with the cold section 2A flow transmitter; the cold section 2B temporary differential pressure transmitter is used for being connected with the cold section 2B flow transmitter; the I-ring hot section temporary differential pressure transmitter 1 is used for being connected with the I-ring hot section flow transmitter A; the I-ring hot section temporary differential pressure transmitter 2 is used for being connected with the I-ring hot section flow transmitter B; the II-ring hot section temporary differential pressure transmitter 1 is used for being connected with the II-ring hot section flow transmitter A; the II-ring hot section temporary differential pressure transmitter 2 is used for being connected with the II-ring hot section flow transmitter B; the data acquisition system comprises a first data acquisition system, and the first data acquisition system is connected with the cold section 1A temporary differential pressure transmitter, the cold section 1B temporary differential pressure transmitter, the cold section 2A temporary differential pressure transmitter, the cold section 2B temporary differential pressure transmitter, the ring I hot section temporary differential pressure transmitter 1, the ring I hot section temporary differential pressure transmitter 2, the ring II hot section temporary differential pressure transmitter 1 and the ring II hot section temporary differential pressure transmitter 2 and is used for acquiring differential pressure data; the second data acquisition system is connected with the main pump circuit breaker and used for acquiring and shielding the pump stop time of the main pump; the sampling frequency of the first data acquisition system is 10 Hz; the sampling frequency of the second data acquisition system is 1000 Hz; the main pump circuit breaker uses the main pump logic tripping of the main pump of the power plant during the high outage of the bearing water temperature of the main pump;
l2, performing a hydraulic test on the temporary instrument;
l3, starting and shielding the main pump to operate for a period of time, and collecting related test data;
l4, stopping the shielded main pump to enable the shielded main pump to enter an idling state, and collecting related test data;
in steps L3 and L4, it is further necessary to acquire flow data of a loop through a formal instrument control system of the power plant, where the formal instrument control system of the power plant is connected to the cold leg 1A flow transmitter, the cold leg 1B flow transmitter, the cold leg 2A flow transmitter, the cold leg 2B flow transmitter, the loop i hot leg flow transmitter a, the loop i hot leg flow transmitter B, the loop ii hot leg flow transmitter a, and the loop ii hot leg flow transmitter B; collecting temperature and pressure of a loop and shielding rotation speed, vibration, bearing water temperature, voltage and current data of a main pump through a formal instrument control system of the power plant;
l5, shielding the main pump to stop idling;
l6, calculating an idling flow curve according to the collected test data; specifically, according to the direct proportion relation between the pressure difference and the flow square, an idling flow curve is calculated by using a normalized flow method to judge whether the idling performance of the shielding main pump meets the acceptance criterion; or according to the direct relation between the pressure difference and the flow square, calculating an idling time constant by using a time constant method to judge whether the idling performance of the shielding main pump meets the acceptance criterion;
l7 removing the temporary meter and data acquisition system.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201911138647.XA CN110797129B (en) | 2019-11-20 | 2019-11-20 | Idling test method for shielded main pump of nuclear power plant |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201911138647.XA CN110797129B (en) | 2019-11-20 | 2019-11-20 | Idling test method for shielded main pump of nuclear power plant |
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| CN110797129A CN110797129A (en) | 2020-02-14 |
| CN110797129B true CN110797129B (en) | 2021-06-11 |
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2019
- 2019-11-20 CN CN201911138647.XA patent/CN110797129B/en active Active
Patent Citations (5)
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| EP0017685B1 (en) * | 1979-04-23 | 1984-03-14 | Westinghouse Electric Corporation | Pump drive assembly for liquid metal reactor |
| JPH0235397A (en) * | 1988-07-25 | 1990-02-05 | Toshiba Corp | Operation control device of fast breeder |
| CN103855890A (en) * | 2012-12-03 | 2014-06-11 | 中核核电运行管理有限公司 | Outer rotor type driving motor of main coolant pump |
| CN103246205A (en) * | 2013-05-14 | 2013-08-14 | 上海交通大学 | Nuclear reactor outage analog system and method thereof |
| CN110714927A (en) * | 2019-10-08 | 2020-01-21 | 中国船舶重工集团公司第七一九研究所 | Shaftless shield pump with idling function suitable for small marine reactor |
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