CN212847701U - Flow resistance test temporary measure system of passive reactor core cooling system - Google Patents
Flow resistance test temporary measure system of passive reactor core cooling system Download PDFInfo
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- CN212847701U CN212847701U CN202020549069.0U CN202020549069U CN212847701U CN 212847701 U CN212847701 U CN 212847701U CN 202020549069 U CN202020549069 U CN 202020549069U CN 212847701 U CN212847701 U CN 212847701U
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The utility model discloses an experimental system of being measured of passive reactor core cooling system flow resistance, include: the water supply system comprises a water supply pipeline for connecting a water source to a user box body, a water supply pump set for providing power, a drainage pipeline from the user box body to a drainage pit, a valve, an instrument, a pipe fitting and other accessories, wherein water replenishing paths of different user box bodies are controlled on line according to different valves, data acquisition is carried out through a flow meter arranged on the drainage pipeline, and then the purposes of data analysis and test result evaluation are achieved. The utility model discloses the integration degree is high, the portability is strong, can wholly dismantle directly to be used for the same passive reactor core cooling system flow resistance of type nuclear power plant experimental, or with the scheme for guiding and be used for follow-up similar AP/CAP passive reactor core cooling system debugging test of type nuclear power plant.
Description
Technical Field
The utility model belongs to nuclear power plant's nuclear island system debugging faces the measure scheme, and the special integration of in particular to passive reactor core cooling system flow resistance test faces the measure and arranges.
Background
The passive core cooling system (hereinafter referred to as PXS) is a special safety system of an AP/CAP series nuclear power plant, is a key point and a difficult point of nuclear island debugging. In view of the passive design of the PXS, no pump or the like is used as a driving force in the design, the flow resistance of the piping system becomes a determining factor influencing the safety injection capability, and the flow resistance cannot be directly measured, so that the flow resistance test needs to be performed on each safety injection path to verify that the flow resistance of the piping system meets the design requirements.
According to experience, the PXS flow resistance test has the following characteristics:
the test items are many: as a special safety system for an AP/CAP series nuclear power plant, the function of the special safety system needs to be comprehensively verified to meet the design requirement, the passive design is realized, the adjustment requirement on a pore plate is higher, and part of flow resistance tests often need to be executed for multiple times to pass the acceptance criterion;
the temporary measures are complicated: the flow resistance test has high requirements on measurement accuracy, and the system is not provided with a flow meter, so a large number of temporary meters are installed during the flow resistance test. As a safety system, part of the flow channels are directly discharged to the containment after an accident, and during debugging, a safe flow channel path must be established through temporary measures;
long water replenishing time consumption: the flow resistance test has short duration, usually only several minutes of data acquisition time, a related box body needs to be filled with water before the test, and a formal system does not have the condition of water supplement for the box body during the flow resistance test, so a desalted water distribution system (called DWS below) needs to be used for supplementing water for the box body through temporary measures, and the water supplement consumes long time;
the progress pressure is large: the PXS system is directly connected with a loop, the flow resistance test boundaries of the PXS system are all located in the loop hydrostatic test boundary, the completion of the flow resistance test is an important prerequisite for the loop hydrostatic test, the loop hydrostatic test is a major milestone node in a debugging stage, the construction period is short, and the progress pressure is large.
The filling and draining capacity of a nuclear island formal filling and draining system (comprising a demineralized water storage and distribution system DWS, a chemical and volume control system CVS, a nuclear island liquid waste system WLS, a radioactive wastewater drainage system WRS and the like) is limited, and the requirements of field test progress cannot be met. By combining the characteristics of the PXS flow resistance test, a temporary measure mode needs to be adopted, and the establishment of the prerequisite condition of water filling and draining of the flow resistance test is realized.
SUMMERY OF THE UTILITY MODEL
The utility model aims to solve is that current passive core cooling system flow resistance is experimental to face the measure facility a lot of, arranges the dispersion, and installation and administrative cost are high, fills the problem of drainage length consuming time. Therefore the utility model provides an experimental system of arranging of passive reactor core cooling system flow resistance, include: the system comprises a water supply source, a user box body, a water supply pipeline, a water supply pump set, a drainage pipeline and a measuring device;
the water supply source can be a demineralized water storage and distribution system water tank (A), a demineralized water source quick connector (B);
the user box body can be a built-in refueling water tank (C), a reactor core water replenishing tank (D), a safety injection tank (E), a containment pressure vessel reinforcing rib water collecting tank (H) and a ring hanging beam water collecting tank (I);
the water supply pipeline is a water supply main pipe which is connected between the water supply source and the users needing water supplement during the flow resistance test;
the water supply pump set (P1, P2) is positioned between the water supply source and the user box and is used for providing water replenishing power;
the drainage pipeline is from the user box body to a drainage pit and provides a passage for a drainage test of the user box body;
the measuring instruments of the measuring device are arranged on the water supply pipeline and the water discharge pipeline and comprise a water supply parameter measuring instrument and a water discharge flow measuring instrument.
Preferably, the measuring device comprises a water supply pump set outlet pressure gauge, a water supply line flowmeter, a box body drainage accumulation flowmeter and a turbine flowmeter.
Preferably, the feed pump group (P1, P2) consists of two feed pumps connected in parallel.
Preferably, the feed water pump unit (P1, P2) is provided with a recirculation line to avoid cavitation of the pump unit when the feed water flow is small during initial startup.
Preferably, the feed pump group (P1, P2) is provided with a hydrophobic line and a vent line.
Preferably, the water supply main pipe of the outlet of the given pump set (P1, P2) is provided with a pressure gauge P for monitoring the pressure of the outlet of the pump set and a flow meter F1 for monitoring the flow rate of the supplied water.
Preferably, set up interim manhole moisturizing pipeline on reactor core moisturizing case (D), interim manhole moisturizing pipeline with the main pipe that supplies water links to each other, can reach and improve the moisturizing flow.
Preferably, the reactor core water supplementing tank (D) and the safety injection tank (E) are connected with a rapid joint (B) of a demineralized water source in parallel, six valve groups and corresponding bridging pipelines are arranged on the pipelines, and the six valve groups and the corresponding bridging pipelines share one section of the drainage pipeline for drainage.
Preferably, the water supply pipeline and the water discharge pipeline are made of stainless steel.
The utility model discloses according to passive reactor core cooling system's test method and system design, through facing each box moisturizing to the optimization of measure, facing the adjustment of measure pipeline size and instrument lectotype, reduce corresponding instrument, pipeline and pipe fitting, practice thrift equipment purchasing cost to realized facing the integration of measure, improved and faced reliability, the security of measure, be convenient for simultaneously face measure implementation and management, the debugging personnel operation of also being convenient for is favorable to experimental execution. The utility model discloses the integration degree is high, the portability is strong, can wholly dismantle directly to be used for the same passive reactor core cooling system flow resistance of type nuclear power plant experimental, or with the scheme for guiding and be used for follow-up similar AP/CAP passive reactor core cooling system debugging test of type nuclear power plant.
Drawings
FIG. 1 is a schematic flow chart of a flow resistance test approach for a passive core cooling system;
FIG. 2 is a schematic diagram of a core water supplement tank (CMT) and an auxiliary injection tank (ACC) water supplement measure used in a flow resistance test of a conventional passive core cooling system;
FIG. 3 is a schematic diagram of a core water supplement tank (CMT) and an injection tank (ACC) for a flow resistance test of the passive core cooling system according to the present invention;
FIG. 4 is a schematic diagram of a structure of a temporary manhole water supply pipeline of a core water supply tank (CMT).
Detailed Description
In order to make the present invention more comprehensible, preferred embodiments accompanied with relevant data are described in detail below.
Fig. 1 to 4 are respectively an integrated temporary solution schematic diagram, a conventional passive core cooling system flow resistance test core water supplement tank (CMT) and safety injection tank (ACC) water supplement temporary solution schematic diagram, an optimized passive core cooling system flow resistance test core water supplement tank (CMT) and safety injection tank (ACC) water supplement temporary solution schematic diagram, and a core water supplement tank (CMT) temporary manhole water supplement pipeline structure schematic diagram provided in this embodiment, and include:
a demineralized water storage and distribution system water tank a, a demineralized water source quick connector B, as a water supply source for this embodiment;
a built-in refueling water tank C, a reactor core water replenishing tank D, a safety injection tank E, a containment pressure vessel (CV) reinforcing rib water collecting tank H and a ring hanging beam water collecting tank I are used as water supply users in the embodiment;
the water feed pump set is formed by connecting two water feed pumps P1 and P2 in parallel and provides a power source for water supply in the embodiment;
the water feed pump set and the water tank of the demineralized water storage and distribution system are provided with manual isolation valves V1 and V2 which are connected in parallel;
a pressure gauge P for monitoring the outlet pressure of the pump set and a flowmeter F1 for monitoring the water supply flow are arranged in the water supply main pipe at the outlet of the pump set;
the main water supply pipe is provided with a branch pipe to the built-in refueling water tank C, and a manual flow regulating valve V14 is arranged on the pipeline;
each row of reactor core water replenishing tanks D and the safety injection tank E are provided with an additional water replenishing pipeline which is connected to a demineralized water source quick connector B;
a water main pipe is supplied to a CV reinforcing rib water collecting tank H, a manual flow regulating valve V16 and a turbine flowmeter F3 for acquiring flow data during a test are arranged on the pipeline;
the water supply main pipe is connected to the water collecting tank I of the ring hanging beam, and a manual flow regulating valve V17 and a turbine flowmeter F4 for acquiring flow data during the test are arranged on the pipeline.
In a specific embodiment, the water supply line is stainless steel;
in a specific embodiment, the valve and the pipe fitting are made of stainless steel;
in a specific embodiment, the feed pump group is provided with a drain line and drain valve V3, a vent line and vent valves V7, V8;
in a specific embodiment, each water supply pump outlet is provided with a manual stop valve V5, V6 for adjusting the flow;
in a specific embodiment, a check valve V9, V10 is arranged at the downstream of each feed pump outlet stop valve;
in a particular embodiment, the feed pump set recirculation line is provided with a check valve V11;
in a specific embodiment, a temporary manhole water replenishing pipeline is arranged in the core water replenishing tank CMT and is connected to a water replenishing main pipe, and a manual isolation valve V15 is arranged on the pipeline;
in a specific embodiment, each row of core water replenishing tanks D and the safety injection tanks E share one path of water supply main pipe and water drainage main pipe, six valve groups Q1-Q6 are arranged in a bridging mode, operation can be simultaneously performed during one tank water replenishing test and one tank water drainage test, a water drainage pipeline is provided with an accumulated flowmeter F2 for collecting flow data during the test, and finally water is drained to a rainwater well G.
The use method of the CAP1400 passive core cooling system flow resistance test integrated temporary measure comprises the following steps:
s1: water is taken from a water tank of a demineralized water storage and distribution system through a water feed pump set arranged outside a containment, and water is respectively supplied to a built-in refueling water tank C, a reactor core water replenishing tank D, a safety injection tank E, CV reinforcing rib water collecting tank H and a ring hanging beam water collecting tank I through different valve state control, so that test preconditions are established;
s2: monitoring an integrated temporary measure running state by a pressure gauge P and a flow gauge F1 arranged on a pump set outlet main pipe in the water supply process;
s3: the reactor core water replenishing tank D and the safety injection tank E of each sequence are arranged in a bridging mode through six valve groups Q1-Q6, and the simultaneous operation of one tank water replenishing test and one tank water draining test can be achieved;
s4: taking the example that the reactor core water supplementing tank D supplements water and the safety injection tank E executes a discharge test, the manual valves V15, Q1, Q2, Q5 and Q6 are opened, Q3 and Q4 are closed, the reactor core water supplementing tank D can supplement water with the demineralized water source quick connector B through a water supply main pipe, and the safety injection tank E can pass through an accumulated flowmeter F2 for acquiring flow data during the test period through a water drainage pipeline and finally drains water to the catch basin G;
s5: similarly, by opening the manual valves Q1, Q2, Q3, Q4 and closing the V15, Q5, Q6, the core makeup tank D discharge test can be performed while the safety tank E is being replenished with water;
s6: in the CV reinforcing rib water collecting tank H and the ring hanging beam water collecting tank I test, water can be directly supplied by a water supply pump set through a water supply main pipe, data acquisition is carried out through turbine flow meters F3 and F4 arranged on a discharge pipeline, and data analysis and test result evaluation are carried out.
While the preferred embodiments of the present invention have been described, additional variations and modifications in those embodiments may occur to those skilled in the art once they learn of the basic inventive concepts. It is therefore intended that the appended claims be interpreted as including the preferred embodiment and all such alterations and modifications as fall within the scope of the invention. Various modifications and alterations of this invention may be made by those skilled in the art without departing from the spirit and scope of this invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims and their equivalents, the present invention is also intended to include such modifications and variations.
Claims (9)
1. A passive reactor core cooling system flow resistance test temporary measure system is characterized by comprising a water supply source, a user box body, a water supply pipeline, a water supply pump set, a water drainage pipeline and a measuring device;
the water supply source can be a demineralized water storage and distribution system water tank (A), a demineralized water source quick connector (B);
the user box body can be a built-in refueling water tank (C), a reactor core water replenishing tank (D), a safety injection tank (E), a containment pressure vessel reinforcing rib water collecting tank (H) and a ring hanging beam water collecting tank (I);
the water supply pipeline is a water supply main pipe which is connected between the water supply source and the users needing water supplement during the flow resistance test;
the water supply pump set (P1, P2) is positioned between the water supply source and the user box and is used for providing water replenishing power;
the drainage pipeline is from the user box body to a drainage pit and provides a passage for a drainage test of the user box body;
the measuring instruments of the measuring device are arranged on the water supply pipeline and the water discharge pipeline and comprise a water supply parameter measuring instrument and a water discharge flow measuring instrument.
2. The passive core cooling system flow resistance test clinical measure system according to claim 1, wherein the measuring device comprises a water supply pump set outlet pressure gauge, a water supply line flowmeter, a tank body drainage accumulation flowmeter and a turbine flowmeter.
3. The passive core cooling system flow resistance test temporary measure system according to claim 1, wherein the feed pump group (P1, P2) consists of two feed pumps connected in parallel.
4. The passive core cooling system flow resistance test clinical system according to claim 1, wherein the feed pump group (P1, P2) is provided with a recirculation line to avoid cavitation of the pump group when the feed water flow is small at the initial startup.
5. The passive core cooling system flow resistance test clinical system according to claim 1, characterized in that the feed pump group (P1, P2) is provided with a drain line and a vent line.
6. The passive reactor core cooling system flow resistance test clinical measure system as claimed in claim 1, wherein the water supply main pipe at the outlet of the water supply pump group (P1, P2) is provided with a pressure gauge P for monitoring the outlet pressure of the pump group and a flow meter F1 for monitoring the flow rate of the water supply.
7. The passive reactor core cooling system flow resistance test temporary measure system according to claim 1, wherein a temporary manhole water replenishing pipeline is arranged on the reactor core water replenishing tank (D), and the temporary manhole water replenishing pipeline is connected with the main water supply pipe, so that the purpose of improving water replenishing flow can be achieved.
8. The passive reactor core cooling system flow resistance test temporary measure system as claimed in claim 1, wherein the reactor core water supply tank (D) and the safety injection tank (E) are connected in parallel with a rapid joint (B) of a demineralized water source, six valve groups and corresponding bridging pipelines are arranged on the pipelines, and the drainage pipelines share one section for drainage.
9. The passive core cooling system flow resistance test clinical measure system of claim 1, wherein the water supply line and the water discharge line are made of stainless steel.
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| CN111370151A (en) * | 2020-04-14 | 2020-07-03 | 国核工程有限公司 | Passive reactor core cooling system flow resistance test temporary measure system and use method |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111370151A (en) * | 2020-04-14 | 2020-07-03 | 国核工程有限公司 | Passive reactor core cooling system flow resistance test temporary measure system and use method |
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| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20220608 Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: STATE NUCLEAR POWER ENGINEERING Co. Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| TR01 | Transfer of patent right | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| CP01 | Change in the name or title of a patent holder |