CN-121983362-A - Pipeline elbow erosion experimental device and method for nuclear reactor

CN121983362ACN 121983362 ACN121983362 ACN 121983362ACN-121983362-A

Abstract

The invention discloses a pipe elbow erosion experimental device and method for a nuclear reactor, wherein the experimental device comprises a main loop system for forming a circulation loop of high-temperature liquid metal, a test section, an oxygen control system, a feeding system and a central control system, wherein the main loop system is externally connected with a liquid metal source, the test section is arranged in the main loop system and is provided with at least one test branch for installing an elbow to be tested, the oxygen control system is used for monitoring and adjusting the oxygen concentration in the liquid metal and is connected with the main loop system, the feeding system is used for adding solid particles into the main loop system and is connected with the main loop system, and the central control system is respectively and electrically connected with the main loop system and the oxygen control system, controls the operation and parameters of the main loop system and the oxygen control system and collects related data. The invention can accurately simulate the complex operation environment of the liquid metal pile with high temperature, oxygen control and solid particulate matter content, realize the systematic research of the erosion characteristics of the pipe elbow, and provide a reliable experimental platform for researching the erosion mechanism and evaluating the material performance.

Inventors

XIAO MENGFAN
LIU JINJIA
GUO SHUSHENG
ZHANG WENJUN
PENG HAO
CHEN LI
ZHANG MING
YE LIN

Assignees

中广核研究院有限公司
中广核南方科技有限公司
中国广核电力股份有限公司

Dates

Publication Date: 20260505
Application Date: 20260112

Claims (15)

1. A pipe elbow erosion test apparatus for a nuclear reactor, comprising: a main loop system (1) for forming a circulation loop of high-temperature liquid metal, wherein the main loop system (1) is externally connected with a liquid metal source; The test section (2) is arranged in the main loop system (1) and is provided with at least one test branch (21) for installing the elbow (212) to be tested; an oxygen control system for monitoring and regulating the oxygen concentration in the liquid metal, connected to the main circuit system (1); The feeding system is used for adding solid particles into the main loop system (1) and is connected with the main loop system (1); And the central control system (5) is respectively and electrically connected with the main loop system (1) and the oxygen control system, controls the operation and the parameters of the main loop system (1) and the oxygen control system, and collects related data.
2. The pipe elbow washout experimental device for nuclear reactor according to claim 1, wherein the main circuit system (1) comprises an electromagnetic pump (12) for driving the circulation of liquid metal and a heater one (16) for heating the liquid metal, the electromagnetic pump (12) and the heater one (16) being electrically connected to the central control system (5), respectively.
3. The pipe elbow washout experimental device for nuclear reactor according to claim 1, wherein the main loop system (1) further comprises a flow meter (13) for measuring a liquid metal mass flow rate and a plurality of temperature transmitters for monitoring temperature, the temperature transmitters are arranged at a plurality of key points of the main loop system (1), and the flow meter (13) and the temperature transmitters are electrically connected with the central control system (5), respectively.
4. The pipe elbow washout testing device for nuclear reactor according to claim 1, wherein the main circuit system (1) further comprises an expansion tank (14), and a flow stabilizer for stabilizing fluid and reducing solid particulate matter accumulation is arranged inside the expansion tank (14); And, the oxygen control system includes: An oxygen control box (31) connected with the expansion tank (14) through a pipeline; An oxygen sensor (32) which is arranged in the expansion tank (14) or on a pipeline communicated with the expansion tank (14) and is used for monitoring the oxygen concentration of the liquid metal in real time and is electrically connected with the central control system (5); And the air source supply module is communicated with the oxygen control box (31) and is used for providing mixed gas with a specific proportion so as to control the oxygen content in the main loop system (1).
5. The pipe elbow erosion experiment device for a nuclear reactor according to claim 4, wherein the gas source supply module comprises an argon gas source (331) and an oxygen gas source, the argon gas source (331) and the oxygen gas source are respectively communicated with the oxygen control box (31) through gas path valves and are electrically connected with the central control system (5); The oxygen control box (31) is internally provided with a gas mixing unit which is used for mixing argon from the argon source (331) with oxygen from the oxygen source according to a preset proportion to form mixed gas and conveying the mixed gas to the expansion box (14).
6. The piping elbow washout testing device for a nuclear reactor according to claim 4, wherein the gas supply module further comprises an inert gas source and a connected first gas source branch, the first gas source branch being in communication with the expansion tank (14) for providing an inert gas environment for the expansion tank (14).
7. The pipe elbow washout test apparatus for nuclear reactor according to claim 4, wherein the gas supply module comprises a premixed gas source (332) communicating with the oxygen control tank (31), wherein the premixed gas source (332) is filled with an argon-oxygen mixed gas having a fixed preset oxygen concentration, and wherein the oxygen control tank (31) adjusts the oxygen content dissolved in the liquid metal by controlling the supply flow rate of the premixed gas source (332).
8. The pipe elbow erosion experiment device for a nuclear reactor according to claim 1, wherein the feeding system comprises a particulate feeding port (4) arranged on the main loop system (1) and an openable sealing structure, the particulate feeding port (4) is positioned at the upstream of the experiment section (2), and the sealing structure is detachably and hermetically covered on the particulate feeding port (4).
9. The pipe elbow erosion experiment device for a nuclear reactor according to claim 1, further comprising a liquid tank (6) for generating liquid metal and a waste liquid tank (7) for recovering waste liquid after the experiment, wherein the liquid tank (6) and the waste liquid tank (7) are connected with the main circuit system (1) through a pipeline and a valve, respectively.
10. The apparatus according to claim 9, further comprising an inert gas source connected to the tank (6), wherein the liquid metal in the tank (6) is injected into the main circuit system (1) by pressurizing the inert gas source with an inert gas output.
11. The apparatus according to claim 1, further comprising a thermal insulation structure that is tightly fitted on part or all of the outer walls of the main circuit system (1) and/or the test section (2); The insulation structure comprises a heat tracing band and/or an insulation layer.
12. The pipe elbow washout testing apparatus for nuclear reactors according to any one of claims 1 to 11, wherein the central control system (5) integrates data acquisition, equipment control, electrical protection and fault alarm functions.
13. The pipe bend erosion test device for nuclear reactor according to any one of claims 1 to 11, wherein the test section (2) comprises at least two parallel test branches (21), the parallel test branches (21) are connected in series in the main loop system (1) as a whole, and an isolation valve (211) is respectively arranged at an inlet end and an outlet end of each test branch (21), and a specific test branch (21) is selectively connected by controlling the opening and closing of the isolation valve (211).
14. A method of performing a pipe bend erosion test for a nuclear reactor, characterized by using the pipe bend erosion test device for a nuclear reactor according to any one of claims 1 to 13, comprising the steps of: S10, providing an inert gas environment for the main loop system (1) and the test section (2) through an oxygen control system or an external inert gas source; S20, filling the main loop system (1) with liquid metal; S30, heating the liquid metal to a preset temperature through a first heater (16) of the main loop system (1) and maintaining stability; s40, adjusting the oxygen content of the main loop system (1) through the oxygen control system and maintaining the oxygen content at a preset concentration; s50, a certain amount of solid particles are put into the main loop system (1) through the feeding system; s60, starting an electromagnetic pump (12) of the main loop system (1) to perform a cyclic erosion experiment for a preset time on the test branch (21); and S70, monitoring the temperature and the oxygen content of the liquid metal in the experimental process, and regulating the temperature of the liquid metal to be stable at the preset temperature and the oxygen content to be stable at the preset concentration through the central control system (5).
15. The method according to claim 14, characterized in that the test section (2) comprises three parallel-arranged test branches (21), namely a first test branch, a second test branch and a third test branch, wherein the three parallel-arranged test branches (21) are connected in series as a whole in the main circuit system (1), and an isolation valve (211) is respectively arranged at the inlet end and the outlet end of each test branch (21); step S60 includes: s61, opening isolation valves (211) at an inlet end and an outlet end of the first test branch, closing the isolation valves (211) of the second test branch and the third test branch, and starting the electromagnetic pump (12) to perform a cyclic erosion experiment for a first preset time; S62, closing isolation valves (211) at the inlet end and the outlet end of the first test branch after the experiment of the first test branch is completed, and then opening the isolation valves (211) at the inlet end and the outlet end of the second test branch to perform a cyclic erosion experiment for a second preset time; S63, closing isolation valves (211) at the inlet end and the outlet end of the second test branch after the experiment of the second test branch is completed, and then opening the isolation valves (211) at the inlet end and the outlet end of the third test branch to perform a cyclic erosion experiment for a third preset time.

Description

Pipeline elbow erosion experimental device and method for nuclear reactor Technical Field The invention relates to the technical field of reactors, in particular to a device and a method for a pipeline elbow erosion experiment for a nuclear reactor. Background The liquid metal stack adopts liquid metal (such as lead and lead bismuth eutectic alloy) as a coolant, and metal solid particles generated by corrosion and abrasion can be carried in the operation process of the reactor. These solid particles flow with the liquid metal, producing a continuous erosion effect on the pipe bends and the like, resulting in reduced wall thickness and threatening the safe operation of the reactor. At present, an erosion test device for common fluid (such as water and air) is mature, but the special environment of high-temperature liquid metal is difficult to simulate, and the actual erosion mechanism in a liquid metal stack cannot be accurately researched. Disclosure of Invention The invention aims to solve the technical problem of providing a device and a method for a pipeline elbow erosion experiment for a nuclear reactor. The technical scheme adopted by the invention for solving the technical problems is that a pipeline elbow erosion experimental device for a nuclear reactor is constructed, comprising: A main loop system for forming a circulation loop of high temperature liquid metal, the main loop system being externally connected with a liquid metal source; the test section is arranged in the main loop system and is provided with at least one test branch for installing the elbow to be tested; An oxygen control system for monitoring and regulating the oxygen concentration in the liquid metal, connected to the main loop system; the feeding system is used for adding solid particles into the main loop system and is connected with the main loop system; And the central control system is respectively and electrically connected with the main loop system and the oxygen control system, controls the operation and the parameters of the main loop system and the oxygen control system, and collects related data. Further, the main loop system comprises an electromagnetic pump for driving the liquid metal to circulate and a first heater for heating the liquid metal, and the electromagnetic pump and the first heater are respectively and electrically connected with the central control system. Further, the main loop system further comprises a flowmeter for measuring the mass flow rate of the liquid metal and a plurality of temperature transmitters for monitoring the temperature, wherein the temperature transmitters are arranged at a plurality of key points of the main loop system, and the flowmeter and the temperature transmitters are respectively and electrically connected with the central control system. Further, the main loop system also comprises an expansion tank, and a flow stabilizer for stabilizing fluid and reducing solid particulate matter accumulation is arranged in the expansion tank; And, the oxygen control system includes: The oxygen control box is connected with the expansion box through a pipeline; The oxygen sensor is arranged in the expansion tank or on a pipeline communicated with the expansion tank, is used for monitoring the oxygen concentration of the liquid metal in real time and is electrically connected with the central control system; And the air source supply module is communicated with the oxygen control box and is used for providing mixed gas with a specific proportion so as to control the oxygen content in the main loop system. Further, the air source supply module comprises an argon air source and an oxygen air source, and the argon air source and the oxygen air source are respectively communicated with the oxygen control box through air passage valves and are electrically connected with the central control system; The oxygen control box is internally provided with a gas mixing unit which is used for mixing argon from the argon source with oxygen from the oxygen source according to a preset proportion to form mixed gas and conveying the mixed gas to the expansion box. Further, the gas source supply module further comprises an inert gas source and a first gas source branch connected with the inert gas source, and the first gas source branch is communicated with the expansion tank and is used for providing an inert gas environment for the expansion tank. Further, the gas source supply module comprises a pre-mixed gas source communicated with the oxygen control box, wherein the pre-mixed gas source is filled with argon-oxygen mixed gas with fixed preset oxygen concentration, and the oxygen control box regulates the oxygen content dissolved in the liquid metal by controlling the supply flow of the pre-mixed gas source. Further, the feeding system comprises a particulate matter feeding port and a sealing structure capable of being opened and closed, wherein the particulate matter feeding port is arranged on the m