CN109473184B - Embedded lead bismuth alloy loop for fuel irradiation test - Google Patents
Embedded lead bismuth alloy loop for fuel irradiation test Download PDFInfo
- Publication number
- CN109473184B CN109473184B CN201811343356.XA CN201811343356A CN109473184B CN 109473184 B CN109473184 B CN 109473184B CN 201811343356 A CN201811343356 A CN 201811343356A CN 109473184 B CN109473184 B CN 109473184B
- Authority
- CN
- China
- Prior art keywords
- lbe
- loop
- water
- cooling water
- tank
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/22—Structural association of coolant tubes with headers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses an embedded lead-bismuth alloy loop for a fuel irradiation test, which comprises an in-pile device, an LBE loop and a water loop, wherein the in-pile device sequentially comprises a heat insulation pipe, a water loop pressure pipe, a water shunt pipe, an LBE loop pressure pipe, an LBE shunt pipe and a test section from outside to inside; the water loop comprises a cooling water outlet and a cooling water inlet, the cooling water outlet and the cooling water inlet and the in-pile device form a cooling circulation loop, and a water loop cooler, a circulation pump and a heater are sequentially arranged between the cooling water outlet and the cooling water inlet. The embedded lead-bismuth alloy loop can be used for performing an LBE (long-bundle-element) stack fuel element performance verification test.
Description
Technical Field
The invention relates to the technical field of nuclear reactor fuel irradiation, in particular to an embedded lead bismuth alloy loop for a fuel irradiation test.
Background
The lead bismuth alloy/lead cooling fast reactor is one of 6 4 th generation advanced nuclear energy systems selected by the 4 th generation nuclear energy forum. The lead-bismuth alloy/lead cooling fast reactor not only meets the requirements of a 4 th generation nuclear energy system, but also has certain operation and use experience, and is one of hot spots of the current advanced nuclear energy system research. Research and design of a reactor and an accelerator driving subcritical system using a Lead-bismuth Eutectic (LBE) as a coolant are widely carried out by domestic and foreign research institutions.
Liquid lead bismuth alloys (LBE) have many advantageous properties as a reactor coolant: 1) chemical inertness with water and air; 2) low steam pressure in the operating temperature range; 3) a high melting point; 4) a large atomic number; 5) excellent neutron performance-low neutron absorption. However, there are still some challenges that are not fully addressed using LBE as a coolant. For example, LBEs can be prone to corrosion of materials at high temperatures, dissolved oxygen control in LBEs, localized deposition of corrosion products, and the like. Additionally, the bismuth-209 nucleus in an LBE absorbs neutrons to produce polonium-210 (half-life about 138 days), polonium-210 having
The radioactivity and volatility are strong, and great radioactive hazard exists.
At present, few researches on compatibility of fuel, materials and LBE under irradiation conditions are carried out, and the influence of combined effects of irradiation and LBE corrosion is a high priority research and development requirement. For the development of a specific stack type, a fuel element performance verification test for highly reducing an actual thermal hydraulic environment is a key step. At present, no LBE cooling reactor can be operated in China, so a fuel irradiation test loop (called LBE fuel irradiation test loop for short) adopting LBE as a coolant is an indispensable facility for performing an LBE reactor fuel element performance verification test and is also a basic research facility for LBE cooling reactor fuel research and development. The fuel element irradiation test research is carried out on the LBE fuel irradiation test loop, a test platform and experience technology feedback can be provided for basic scientific research work of the LBE cooling reactor, and therefore the research and development process of a new energy nuclear energy system is effectively promoted.
Disclosure of Invention
The invention aims to provide an embedded lead bismuth alloy loop for a fuel irradiation test, and the embedded lead bismuth alloy loop can be used for performing an LBE (long bundle element) stack fuel element performance verification test.
The invention is realized by the following technical scheme:
an embedded lead-bismuth alloy loop for a fuel irradiation test comprises an in-pile device, an LBE loop and a water loop, wherein the in-pile device sequentially comprises a heat insulation pipe, a water loop pressure pipe, a water shunt pipe, an LBE loop pressure pipe, an LBE shunt pipe and a test section from outside to inside, the LBE loop comprises an LBE outlet and an LBE inlet, the LBE outlet, the LBE inlet and the in-pile device form an LBE circulation loop, LBE in the LBE loop enters an annular gap between the LBE loop pressure pipe and the LBE shunt pipe from the LBE inlet and flows downwards, the LBE in the LBE loop returns upwards at the bottom of the LBE shunt pipe, flows through a channel between the test section and the LBE shunt pipe and finally flows out of the in-pile device through the LBE outlet, an LBE loop cooler, an electromagnetic circulating pump, a flowmeter, a main heater and a expansion tank are sequentially arranged between the LBE outlet and the LBE inlet, and the expansion tank is; the utility model discloses a device of putting in heap is including the LBE return pressure pipe, the water return circuit includes cooling water outlet and cooling water entry, cooling water outlet and cooling water entry and the interior device of heap form cooling circulation circuit, and the annular gap between entering water return pressure pipe and the water reposition of redundant personnel pipe by the cooling water entry in the water return circuit flows down, turns back upwards in water reposition of redundant personnel pipe bottom, and the annular gap between LBE return pressure pipe and the water reposition of redundant personnel pipe flows through LBE return pressure pipe, and the device of putting in heap is flowed out through the cooling water outlet at last, water return circuit cooler, circulating pump and heater have set gradually between cooling water outlet and the cooling water entry.
The electromagnetic circulating pump is used for providing driving force for circulation in an LBE loop; the main heater is used for heating LBE to a temperature level required by the test section; the LBE loop cooler is used for cooling LBE and ensuring the temperature of the LBE to be within the working range of the electromagnetic circulating pump; the expansion tank is used to absorb the volumetric fluctuations of the LBE circuit and is used as the primary operating vessel for the oxygen control system.
The basic flow of the LBE loop is as follows: LBE is driven by an electromagnetic circulating pump, enters a main heater through a flowmeter for heating, then enters an expansion tank containing an oxygen control system for adjusting and controlling the dissolved oxygen of LBE, and flows into an irradiation device in the LBE loop reactor along a main loop pipeline; flowing down the annular gap between the LBE pressure pipe and LBE shunt pipe, LBE heats up in the core active area by nuclear heat release, flows to the return upward at the bottom of LBE pressure pipe, cools the fuel element and further heats up; LBE continuously flows upwards, exchanges heat with LBE in a descending process to obtain primary cooling, and finally flows out from the upper part of the in-reactor device; after being further cooled by the LBE loop cooler, the refrigerant is sucked into the electromagnetic pump to complete the whole circulation.
The LBE loop is provided with a plurality of auxiliary systems, such as an LBE purification system, a fuel element breakage detection system, an LBE leakage monitoring system, a radiation detection system and the like, a pipeline auxiliary heating system and an instrument control system. The fuel element breakage detection system judges whether the test fuel element is broken or not by monitoring gas components in the loop and the expansion tank. LBE leakage monitoring and radiation detection system, monitoring LBE return circuit pipeline whether leaks and LBE whether leaks to the air. The pipe-assisted heating system is used to heat the pipe and the residual LBE in the pipe at start-up of the circuit. The instrument control system is used for measuring and controlling various parameters during testing and providing data and safety signals for loop operation.
The circulating pump is used for providing driving force for water circulation of the loop; the heater is used for heating water to a required inlet temperature level of the stack; the water loop cooler is connected with a secondary cooling water system and used for cooling loop circulating water to a specified temperature level.
The basic flow of the high-temperature high-pressure water loop is as follows: cooling water is driven by a circulating pump, heated by a heater and then enters the in-pile device; the water flows downwards along an annular gap between the water loop pressure pipe and the water shunt pipe, is heated and heated by an internal heat source in a core active area, flows to the return direction upwards near the bottom of the water loop pressure pipe, washes and cools the LBE loop pressure pipe, and takes away heat generated by the whole embedded loop in-reactor device; after the cooling water flows out from the upper part of the in-pile device, the cooling water is cooled by a water loop cooler and then is sucked into a circulating pump to complete the whole circulation.
The invention is mainly characterized in that: integrally placing an in-stack irradiation device containing a test fuel element in an LBE loop in an in-stack device of a high-temperature high-pressure water loop; the temperature and the cooling condition provided by the water loop are utilized to establish the temperature field of the irradiation device in the LBE loop, and the LBE loop is cooled under the normal operation and accident conditions, so that the LBE stack fuel element performance verification test can be carried out through the embedded lead-bismuth alloy loop.
Further, a filter and an LBE purification system are arranged between the LBE loop cooler and the electromagnetic circulating pump in parallel.
The filter is arranged in front of the suction inlet of the electromagnetic circulating pump and is used for filtering solid impurities in LBE and capturing and removing solid corrosion; the LBE purification system is mainly used for removing solid substances in LBE, and ensures LBE quality of a loop in long-term operation together with the oxygen control system.
LBE heats and raises the temperature in the core active area through nuclear heat release, flows to the return direction and flows upwards at the bottom of the LBE pressure pipe, and cools the fuel element to further raise the temperature; LBE continuously flows upwards, exchanges heat with LBE in a descending process to obtain primary cooling, and finally flows out from the upper part of the in-reactor device; after further cooling by the LBE loop cooler, the water is sucked into the electromagnetic circulating pump through the filter and the purification system to complete the whole circulation.
Further, the LBE circuit further comprises a liquid collecting tank, the liquid collecting tank and the electromagnetic circulating pump form a circuit, and the liquid collecting tank is communicated with the melting tank.
The header tank is located at the lowest position of the circuit and is used for collecting most LBE in the circuit when the circuit is not used, and a certain amount of low-temperature LBE exists under the action of the auxiliary heating system; and the melting tank is used for heating and melting the lead-bismuth alloy when the loop is started.
Further, a voltage stabilizer is arranged between the water loop cooler and the circulating pump.
The pressure stabilizer is used for stabilizing the pressure level of the water loop and absorbing the volume fluctuation of the water loop.
After the cooling water flows out from the upper part of the in-pile device, the cooling water is cooled by a water loop cooler, enters a voltage stabilizer and is sucked into a circulating pump to complete the whole circulation.
The high-temperature high-pressure water loop is also provided with a plurality of auxiliary systems, such as a water supplementing system, a secondary cooling water system, a leakage monitoring system and an instrument control system. The water replenishing system is responsible for filling water into a water container in the water loop and filling water into the system before the loop is started; under the normal operation condition of the system, when the coolant is reduced to a fixed value due to normal leakage, the water level low signal of the voltage stabilizer supplements water to the system. The secondary cooling water system provides a final heat sink for the water loop, and meets the water supply requirements of a water loop cooler, a purification system auxiliary heat exchanger, a circulating pump cooling water and the like. The leakage monitoring system is used for monitoring whether the in-pile device of the water loop and the pipeline of the water loop leak or not. The instrument control system is used for measuring and controlling various parameters during testing and providing data and safety signals for loop operation.
Further, the water circuit also comprises a purification system, and a circuit is formed between the purification system and the circulating pump.
The chemical system is used for filtering corrosion products in water and purifying water quality.
And part of the cooling water flows into a purification system bypass through a circulating pump outlet and returns to a circulating pump inlet after water quality purification operation.
Further, the water loop further comprises a pressure accumulation safety injection tank, the pressure accumulation safety injection tank is communicated with the cooling water inlet through a first safety injection valve, and the pressure accumulation safety injection tank is communicated with the cooling water outlet through a second safety injection valve.
When a breach accident occurs in a water loop, a pressure accumulation safety injection tank is used for injecting water into a cooling water outlet and a cooling water inlet of a main pipeline of the water loop at the same time to provide emergency cooling flow, the direction of the breach of the pipeline is automatically judged through signals provided by an instrument control system, and the opening position of the safety injection tank is adjusted to ensure that the emergency cooling water flows through the in-pile device at a high flow rate, so that the safety of a fuel element and the in-pile device is ensured.
Further, the pressure accumulation safety injection tank is communicated with the emergency water tank, and an emergency cooling pump is arranged between the pressure accumulation safety injection tank and the emergency water tank.
After the pressure accumulation safety injection tank is emptied, the emergency cooling pump draws water from the emergency water tank and injects the water into the main pipeline of the water circuit, so that the long-term cooling water flow is ensured.
Further, the electromagnetic circulating pump includes two first electromagnetic circulating pumps and the second electromagnetic circulating pump that connect in parallel and set up, the main heater includes two first main heater and the second main heater that connect in parallel and set up, the water return circuit cooler includes two first water return circuit coolers and the second water return circuit cooler that connect in parallel and set up, the circulating pump includes two first circulating pumps and the second circulating pump that connect in parallel and set up, the heater includes two first heater and the second heater that connect in parallel and set up.
The electromagnetic circulating pump, the main heater, the water loop cooler, the circulating pump and the heater are all in double configuration, and the reliability of the whole embedded lead-bismuth alloy loop is improved.
Compared with the prior art, the invention has the following advantages and beneficial effects:
the invention integrally arranges an in-pile irradiation device containing a test fuel element in an LBE loop in an in-pile device of a high-temperature high-pressure water loop; the temperature and the cooling condition provided by the water loop are utilized to establish the temperature field of the irradiation device in the LBE loop, and the LBE loop is cooled under the normal operation and accident conditions, so that the LBE stack fuel element performance verification test can be carried out through the embedded lead-bismuth alloy loop.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
fig. 1 is a schematic diagram of an embedded lead bismuth alloy loop.
Reference numbers and corresponding part names in the drawings:
1-adiabatic tube, 2-water circuit pressure tube, 3-water shunt tube, 4-LBE circuit pressure tube, 5-LBE shunt tube, 6-test section, 101-LBE outlet, 102-LBE circuit cooler, 103-filter, 104-LBE purification system, 105-first electromagnetic circulation pump, 106-second electromagnetic circulation pump, 107-flowmeter, 108-melting tank, 109-liquid collecting tank, 110-first main heater, 111-second main heater, 112-oxygen control system, 113-expansion tank, 114-LBE inlet, 201-cooling water outlet, 202-first water circuit cooler, 203-second water circuit cooler, 204-pressure stabilizer, 205-purification system, 206-first circulation pump, 207-second circulation pump, 208-a first heater, 209-a second heater, 210-a cooling water inlet, 301-an emergency water tank, 302-an emergency cooling pump, 303-a pressure accumulation safety injection tank, 304-a first safety injection valve and 305-a second safety injection valve.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example (b):
as shown in fig. 1, the embedded lead-bismuth alloy loop for fuel irradiation test of the invention comprises an in-pile device, an LBE loop and a water loop,
the in-stack device comprises an insulation pipe 1, a water circuit pressure pipe 2, a water shunt pipe 3, an LBE circuit pressure pipe 4, an LBE shunt pipe 5 and a test section 6 in sequence from outside to inside, wherein the LBE circuit comprises an LBE outlet 101 and an LBE inlet 114, the LBE outlet 101 and the LBE inlet 114 form an LBE circulation circuit with the in-stack device, LBE in the LBE circuit enters an annular clearance between the LBE circuit pressure pipe 4 and the LBE shunt pipe 5 from the LBE inlet 114 to flow downwards, the LBE in the LBE circuit is folded back and upwards at the bottom of the LBE shunt pipe 5, flows through a channel between the test section 6 and the LBE shunt pipe 5 and finally flows out of the in-stack device through the LBE outlet 101, an LBE circuit cooler 102, an electromagnetic circulating pump, a flow meter 107, a main heater and a expansion tank 113 are arranged between the LBE outlet 101 and the LBE inlet 114 in sequence, and an oxygen control system; the water loop comprises a cooling water outlet 201 and a cooling water inlet 210, the cooling water outlet 201 and the cooling water inlet 210 and the in-stack device form a cooling circulation loop, cooling water in the water loop enters an annular gap between the water loop pressure pipe 2 and the water shunt pipe 3 from the cooling water inlet 210 and flows downwards, the cooling water in the water loop returns upwards at the bottom of the water shunt pipe 3, flows through the annular gap between the LBE loop pressure pipe 4 and the water shunt pipe 3 and finally flows out of the in-stack device through the cooling water outlet 201, and a water loop cooler, a circulating pump and a heater are sequentially arranged between the cooling water outlet 201 and the cooling water inlet 210; a filter 103 and an LBE purification system 104 are arranged between the LBE loop cooler 102 and the electromagnetic circulating pump in parallel; the LBE circuit further comprises a liquid collecting tank 109, the liquid collecting tank 109 and the electromagnetic circulating pump form a circuit, and the liquid collecting tank 109 is communicated with the melting tank 108; a voltage stabilizer 204 is arranged between the loop cooler and the circulating pump; the water circuit further comprises a purification system 205, a circuit is formed between the purification system 205 and the circulating pump; the water loop further comprises a pressure accumulation safety injection tank 303, the pressure accumulation safety injection tank 303 is communicated with the cooling water inlet 210 through a first safety injection valve 304, and the pressure accumulation safety injection tank 303 is communicated with the cooling water outlet 201 through a second safety injection valve 305; the pressure accumulation safety injection tank 303 is communicated with the emergency water tank 301, and an emergency cooling pump 302 is arranged between the pressure accumulation safety injection tank 303 and the emergency water tank 301.
Preferably, the electromagnetic circulation pump includes two first and second electromagnetic circulation pumps 105 and 106 disposed in parallel, the main heater includes two first and second main heaters 110 and 111 disposed in parallel, the water circuit cooler includes two first and second water circuit coolers 202 and 203 disposed in parallel, the circulation pump includes two first and second circulation pumps 206 and 207 disposed in parallel, and the heater includes two first and second heaters 208 and 209 disposed in parallel.
The main functions and operation modes of the embedded lead-bismuth alloy loop are as follows:
(1) simulating the thermal-hydraulic conditions of the LBE reactor to derive the heat release of the test fuel element
The temperature of water in the high-temperature and high-pressure water loop reactor is 270-280 ℃, and the LBE temperature outside the test fuel element is 350-450 ℃ through the radial heat conduction temperature difference; the LBE in-loop LBE flow rate is less than 2m/s and can be adjusted over a wide range to simulate the actual flow rate of the LBE stack. Under normal operating conditions, heat generated by the test fuel element is transferred to the LBE through convective heat transfer; the cooling water is finally transferred to a water loop in a radial heat exchange mode and is taken out of the in-pile device through water circulation. Part of the released heat is taken away by LBE temperature rise; the high temperature LBE flowing out of the test section is cooled by heat exchange with LBE outside the LBE shunt pipe 5 in the ascending flow process, and is further cooled to be below the limit value of the running temperature of the electromagnetic circulating pump by the LBE loop cooler 102 after flowing out of the reactor.
(2) Controlling the dissolved oxygen and impurities in the LBE and establishing the LBE chemical environment meeting the test requirements
The upstream of the inlet of the electromagnetic circulating pump is provided with a filter screen type and a magnetic trap type filter for filtering solid impurities and partial corrosion products in the loop. LBE purification system 104 can sample LBE in the loop for analysis, impurity purification and chemical addition, so that each index of LBE meets the test requirement. The oxygen control system 112 provided with the expansion tank 113 is used for dissolved oxygen control in the entire LBE, effectively controlling corrosion of the LBE and structural materials, and meeting the LBE chemical property requirements of the LBE prototype stack.
(3) Residual heat removal and long-term cooling capacity of device
After LBE loop fuel irradiation test is finished, the radial heat conduction of the irradiation test device is utilized to transfer decay heat release of the fuel elements and materials into water loop cooling water. The water loop is used as the final heat trap for the waste heat of the fuel element. After the reactor is shut down, the cooling water flow and the cooling water temperature of the water loop are gradually reduced, and finally the cooling stage is transited to the operation in the middle section.
(4) Preventing fuel element from overheating and burning under LBE loop accident condition
The system pressure of the LBE circuit is close to the normal pressure, the break release flow of the LBE is very small, and even a tiny break can be blocked due to solidification of the LBE. As a result, LBE circuit breach incidents have little impact on the thermal safety of the fuel elements of the embedded circuit.
When LBE flow of an LBE loop is greatly reduced due to the fault of an electromagnetic circulating pump, the temperature of LBE outside a test fuel element is greatly increased; at the same time, the cooling capacity of the water circuit also rises due to the increase in the radial temperature difference. The calculation result shows that when the flow speed of the LBE loop is greatly reduced by 90 percent from 1.5m/s, the surface temperature of the fuel element is less than the safety limit value of 750 ℃ under the condition of no operation, the radial temperature difference of the LBE pressure pipe is less than 150 ℃ and the highest temperature is less than 430 ℃, the heat conduction of the in-stack test device can be ensured, and the test fuel element is prevented from being burnt out due to overheating.
(5) Prevent fuel element overheating and burning out under water circuit breach accident condition
Under the working condition of a water loop breach accident, the pressure accumulation safety injection tank 303 of the cooling water loop automatically injects water into the cold and heat pipe sections simultaneously so as to provide emergency cooling capacity of the water loop, the direction of the pipeline breach is automatically judged through signals provided by an instrument control system, and the opening positions of the first safety injection valve 304 and the second safety valve 305 are adjusted so as to ensure that emergency cooling water flows through the in-pile device at a large flow rate and ensure the safety of fuel elements and the in-pile device. After the pressure accumulation safety injection tank 303 is emptied, pure water in the emergency water tank 301 is pumped by the emergency cooling pump 302 and is injected into the in-pile device of the water loop, so that the long-term cooling capacity of the whole embedded loop is provided, and the safety of fuel elements is ensured.
(6) Real-time monitoring multiple test parameters and providing multiple safe shutdown signals
The test parameter monitoring system is provided with temperature, flow, pressure, oxygen content and other parameter detectors at different positions of the LBE loop and the in-pile device, so that comprehensive parameter monitoring information is provided, and the operation and safety of the loop are guaranteed. The LBE loop in-pile device has high outlet temperature and low inlet flow signal to trigger the research of pile protection shutdown. The leak detection system of the water loop carries out damage monitoring on the water loop pressure pipe, so that the water loop testing device is completely isolated from the reactor. The water loop is provided with four shutdown protection signals of high outlet temperature, low inlet flow, overhigh outlet pressure and overlow outlet pressure of the examination device, and reactor shutdown is triggered once the loop is abnormal in operation.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (8)
1. An embedded lead-bismuth alloy loop for a fuel irradiation test is characterized by comprising an in-pile device, an LBE loop and a water loop, wherein the in-pile device sequentially comprises a heat insulation pipe (1), a water loop pressure pipe (2), a water shunt pipe (3), an LBE loop pressure pipe (4), an LBE shunt pipe (5) and a test section (6) from outside to inside, the LBE loop comprises an LBE outlet (101) and an LBE inlet (114), the LBE outlet (101), the LBE inlet (114) and the in-pile device form an LBE circulating loop, the LBE in the LBE loop enters an annular gap between the LBE loop pressure pipe (4) and the LBE shunt pipe (5) from the LBE inlet (114) and flows downwards, the LBE in the LBE loop returns upwards at the bottom of the LBE shunt pipe (5), flows through a channel between the test section (6) and the LBE shunt pipe (5) and finally flows out of the in the LBE loop through the LBE outlet (101), and a LBE cooler (102) and a LBE inlet (114) are sequentially arranged between the LBE outlet (101) and the LBE inlet, The system comprises an electromagnetic circulating pump, a flowmeter (107), a main heater and an expansion tank (113), wherein an oxygen control system (112) is arranged on the expansion tank (113); the water loop comprises a cooling water outlet (201) and a cooling water inlet (210), the cooling water outlet (201) and the cooling water inlet (210) form a cooling circulation loop with the in-pile device, cooling water in the water loop flows downwards through an annular gap between a cooling water inlet (210) entering water loop pressure pipe (2) and a water shunt pipe (3), the bottom of the water shunt pipe (3) returns upwards, flows through the annular gap between an LBE loop pressure pipe (4) and the water shunt pipe (3), and finally flows out of the in-pile device through the cooling water outlet (201), and a water loop cooler, a circulating pump and a heater are sequentially arranged between the cooling water outlet (201) and the cooling water inlet (210).
2. The embedded lead-bismuth alloy loop for fuel irradiation test as claimed in claim 1, characterized in that a filter (103) and an LBE purification system (104) are arranged in parallel between the LBE loop cooler (102) and the electromagnetic circulation pump.
3. The embedded lead-bismuth alloy loop for the fuel irradiation test according to claim 1, wherein the LBE loop further comprises a header tank (109), the header tank (109) forms a loop with an electromagnetic circulating pump, and the header tank (109) is communicated with the melting tank (108).
4. The embedded lead-bismuth alloy loop for the fuel irradiation test as claimed in claim 1, wherein a voltage stabilizer (204) is arranged between the water loop cooler and the circulating pump.
5. The embedded lead-bismuth alloy loop for the fuel irradiation test according to claim 1, characterized in that the water loop further comprises a purification system (205), and a loop is formed between the purification system (205) and a circulating pump.
6. The embedded lead-bismuth alloy loop for the fuel irradiation test is characterized by further comprising a pressure accumulation safety injection tank (303), wherein the pressure accumulation safety injection tank (303) is communicated with the cooling water inlet (210) through a first safety injection valve (304), and the pressure accumulation safety injection tank (303) is communicated with the cooling water outlet (201) through a second safety injection valve (305).
7. The embedded lead-bismuth alloy loop for the fuel irradiation test is characterized in that the pressure accumulation safety injection tank (303) is communicated with an emergency water tank (301), and an emergency cooling pump (302) is arranged between the pressure accumulation safety injection tank (303) and the emergency water tank (301).
8. The embedded lead-bismuth alloy loop for the fuel irradiation test according to any one of claims 1 to 7, wherein the electromagnetic circulating pump comprises two first electromagnetic circulating pumps (105) and two second electromagnetic circulating pumps (106) arranged in parallel, the main heater comprises two first main heaters (110) and two second main heaters (111) arranged in parallel, the water loop cooler comprises two first water loop coolers (202) and two second water loop coolers (203) arranged in parallel, the circulating pump comprises two first circulating pumps (206) and two second circulating pumps (207) arranged in parallel, and the heaters comprise two first heaters (208) and two second heaters (209) arranged in parallel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811343356.XA CN109473184B (en) | 2018-11-13 | 2018-11-13 | Embedded lead bismuth alloy loop for fuel irradiation test |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811343356.XA CN109473184B (en) | 2018-11-13 | 2018-11-13 | Embedded lead bismuth alloy loop for fuel irradiation test |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109473184A CN109473184A (en) | 2019-03-15 |
| CN109473184B true CN109473184B (en) | 2020-03-17 |
Family
ID=65671861
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811343356.XA Active CN109473184B (en) | 2018-11-13 | 2018-11-13 | Embedded lead bismuth alloy loop for fuel irradiation test |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109473184B (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110828007B (en) * | 2019-11-18 | 2021-06-29 | 中国核动力研究设计院 | Special voltage stabilizer and pressure control system for reactor irradiation examination loop |
| CN114864120A (en) * | 2022-04-24 | 2022-08-05 | 中国原子能科学研究院 | Oxygen content adjusting module and reaction system |
Family Cites Families (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06242284A (en) * | 1993-02-12 | 1994-09-02 | Nippon Nuclear Fuel Dev Co Ltd | Device for irradiation test |
| JPH11344484A (en) * | 1998-05-29 | 1999-12-14 | Mitsubishi Heavy Ind Ltd | Sodium combustion testing apparatus |
| JP2006047063A (en) * | 2004-08-03 | 2006-02-16 | Mitsubishi Heavy Ind Ltd | Irradiation test reactor |
| DE102006009502B3 (en) * | 2006-02-27 | 2007-08-30 | Framatome Anp Gmbh | Method for testing a fuel rod cladding tube and associated device |
| CN102254577B (en) * | 2011-06-30 | 2013-05-22 | 西安交通大学 | Liquid sodium metal thermohydraulic experimental loop system and using method thereof |
| CN202662302U (en) * | 2012-06-11 | 2013-01-09 | 华北电力大学 | 0-shaped lead-bismuth heat exchange device for achieving double-side flowing heat transfer |
| CN102915777A (en) * | 2012-10-10 | 2013-02-06 | 西安交通大学 | Liquid metal sodium boiling two-phase thermal-hydraulic test loop system and test method thereof |
| CN103413579B (en) * | 2013-07-08 | 2016-04-06 | 华北电力大学 | A kind of natural circulation loop system of lead-bismuth alloy |
| RU2542329C1 (en) * | 2013-09-30 | 2015-02-20 | Открытое Акционерное Общество "Акмэ-Инжиниринг" | Method for intra-loop passivation of steel surfaces of nuclear reactor |
| CN108761022B (en) * | 2018-05-29 | 2023-12-08 | 中广核研究院有限公司 | Liquid lead bismuth alloy thermal hydraulic characteristic and corrosion characteristic experiment system |
-
2018
- 2018-11-13 CN CN201811343356.XA patent/CN109473184B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN109473184A (en) | 2019-03-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US8638898B2 (en) | Emergency core cooling system for pressurized water reactor | |
| Zheng et al. | Water-ingress analysis for the 200áMWe pebble-bed modular high temperature gas-cooled reactor | |
| CN106653107A (en) | Passive decay heat removal system for liquid metal cooling pool type reactor | |
| CN109473184B (en) | Embedded lead bismuth alloy loop for fuel irradiation test | |
| CN104919532A (en) | Method and apparatus for refueling a nuclear reactor having an instrumentation penetration flange | |
| CN102820067B (en) | Natural circulation heat exchanger for discharging waste heat of supercritical water reactor | |
| KR20130026038A (en) | Passive decay heat removal system for liquid metal cooled reactors with enhanced natural circulation capability of reactor pool using a chimney effect | |
| Raqué et al. | Design and 1D analysis of the safety systems for the SCWR fuel qualification test | |
| CN109920564A (en) | A kind of overcritical double helix natural cycle system and method | |
| Choi et al. | Feasibility study of a gas cartridge loop for the versatile test reactor | |
| JP2009186473A (en) | Cold shutdown apparatus for sodium cooled reactor | |
| Giannetti et al. | Phénix transient analysis for the assessment of RELAP5-3D based on dissymmetric test benchmark | |
| Berikbosinov et al. | Development of The Built-In Primary Sodium Purification System for The Advanced BN-1200 Reactor Plant | |
| Polidoro et al. | Preliminary assessment of the thermal interaction among corium and in-vessel core catcher in a large sodium fast reactor | |
| KR102660990B1 (en) | Passive Emergency Core Cooling System of Nuclear power Plant and Cooling Method using the same | |
| Kovtonyuk et al. | Safety of evolutionary reactors: feasibility study for the experimental program of SPES facility | |
| CN209641362U (en) | A kind of overcritical double helix natural cycle system device | |
| Liu et al. | Preliminary safety analysis for the SCWR‐FQT facility | |
| Susyadi | Thermal-hydraulic analysis of SMR with naturally circulating primary system during loss of feed water accident | |
| Mandal et al. | Assessment of Shutdown Systems' performance during postulated Large Break LOCA for 700MWe Pressurized Heavy Water Reactors | |
| Xu et al. | Design and Investigation of Liquid Lead-Bismuth Test Irradiation Loop in Research Reactor | |
| Yue et al. | The Choose of Decay Heat Removal Systems of SFR | |
| Ning et al. | LBLOCA initiated emergency condition analysis for a China three-loop PWR | |
| Polkinghorne et al. | Analysis of an advanced test reactor small-break loss-of-coolant accident with an engineered safety feature to automatically trip the primary coolant pumps | |
| Khan et al. | Transient analysis of integral pressurized water reactor (IPWR) |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |