CN116612909A - Experimental device and method for researching failure behavior of nuclear reactor fuel rod cluster accident - Google Patents
Experimental device and method for researching failure behavior of nuclear reactor fuel rod cluster accident Download PDFInfo
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- CN116612909A CN116612909A CN202310624477.6A CN202310624477A CN116612909A CN 116612909 A CN116612909 A CN 116612909A CN 202310624477 A CN202310624477 A CN 202310624477A CN 116612909 A CN116612909 A CN 116612909A
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- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 25
- 238000000034 method Methods 0.000 title claims description 25
- 238000010438 heat treatment Methods 0.000 claims abstract description 190
- 239000000446 fuel Substances 0.000 claims abstract description 133
- 238000002474 experimental method Methods 0.000 claims abstract description 15
- 239000011159 matrix material Substances 0.000 claims abstract description 12
- 238000005253 cladding Methods 0.000 claims description 58
- 239000007789 gas Substances 0.000 claims description 52
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 45
- 239000011261 inert gas Substances 0.000 claims description 27
- 238000002347 injection Methods 0.000 claims description 23
- 239000007924 injection Substances 0.000 claims description 23
- 238000005259 measurement Methods 0.000 claims description 20
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 claims description 19
- 229910052750 molybdenum Inorganic materials 0.000 claims description 19
- 239000011733 molybdenum Substances 0.000 claims description 19
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims description 17
- 239000000498 cooling water Substances 0.000 claims description 17
- 229910052802 copper Inorganic materials 0.000 claims description 17
- 239000010949 copper Substances 0.000 claims description 17
- 238000010791 quenching Methods 0.000 claims description 16
- 238000001816 cooling Methods 0.000 claims description 13
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- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 5
- 229910052743 krypton Inorganic materials 0.000 description 5
- DNNSSWSSYDEUBZ-UHFFFAOYSA-N krypton atom Chemical compound [Kr] DNNSSWSSYDEUBZ-UHFFFAOYSA-N 0.000 description 5
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 description 4
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- GUVRBAGPIYLISA-UHFFFAOYSA-N tantalum atom Chemical compound [Ta] GUVRBAGPIYLISA-UHFFFAOYSA-N 0.000 description 2
- 229910052726 zirconium Inorganic materials 0.000 description 2
- 239000010963 304 stainless steel Substances 0.000 description 1
- 229910000589 SAE 304 stainless steel Inorganic materials 0.000 description 1
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 1
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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
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
- G21C3/328—Relative disposition of the elements in the bundle lattice
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/334—Assembling, maintenance or repair of the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/34—Spacer grids
-
- 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 application relates to an experimental device for researching failure behaviors of nuclear reactor fuel bundles, which comprises a high-temperature heating furnace, a fuel bundle and accessory equipment, wherein the fuel bundle consists of a plurality of fuel rods, the fuel bundle penetrates through the high-temperature heating furnace along the axis of a channel, the plurality of fuel rods are arranged in a 5 multiplied by 5 matrix, the fuel rods comprise 20 heating rods, 1 non-heating rod and 4 corner rods, the 1 non-heating rod is positioned at the center, and the 4 corner rods are positioned at 4 corners of the matrix; electrodes are respectively arranged at two ends of the fuel rod bundle to heat the fuel rod bundle. The auxiliary equipment carries out environment simulation on the fuel rod bundle in the high-temperature heating furnace, so that oxidation, expansion and failure states and data of the fuel rod bundle under different environments are obtained. Through the arrangement of 25 fuel rods, the application can carry out fuel rod bundle experiments under the influence of oxidation, expansion and failure mechanisms on factors such as flow channel blockage among fuel rod bundles, rod-rod extrusion, heat radiation among rods, axial temperature difference and the like.
Description
Technical Field
The application relates to the technical field of nuclear fuel cladding element performance test experiments, in particular to an experimental device and method for researching failure behavior of nuclear reactor fuel rod cluster accidents.
Background
In nuclear fuel cladding performance test and mechanism model development, an expansion blasting, high-temperature oxidation and quenching failure model of the cladding under the high-temperature condition of serious accidents is generally obtained through a single rod mechanism experiment, and a powerful support is provided for the establishment of an accident acceptance criterion and a serious accident failure criterion. However, the actual situation in the reactor is more complex under the accident environment condition, and the fuel bundles formed by a plurality of fuel rods rapidly bulge, bend and mutually squeeze in the transient heating process under the serious accident, so that the situations of disordered bundle arrangement, bending deformation of the coaming, flow channel blockage and the like are caused. Extrusion between rods and flow channel blockage reduce the contact area between the surface of the cladding and water vapor, reduce the oxidation rate and cause uneven oxidation at each position. In addition, the fuel bundles bulge to different degrees under the action of high temperature and internal pressure, so that the thickness of the cladding wall is thinned to finally generate cracking, and the cracking of the cladding causes oxidation of the inner surface, thereby affecting the structural integrity of the cladding.
Therefore, the oxidation, expansion and failure empirical relation obtained by single rod experiments cannot accurately reflect the influence of factors such as flow channel blockage, rod-rod extrusion, heat radiation between rods, axial temperature difference and the like on oxidation, expansion and failure mechanisms.
Disclosure of Invention
Based on the above, the application provides an experimental device and a method for researching the accident failure behavior of a nuclear reactor fuel rod bundle, which are used for developing the failure mechanism of the fuel rod bundle under the serious accident condition, and carrying out the adaptability correction of the expansion model, the oxidation model and the failure model obtained by single rod experiments under the rod bundle condition. The method specifically comprises the following steps:
the high-temperature heating furnace comprises an upper chamber, a middle cylinder body and a lower chamber which are connected in sequence;
the fuel rod bundles comprise a plurality of fuel rods, the fuel rods penetrate through the upper cavity, the middle cylinder body and the lower cavity, the plurality of fuel rods are uniformly distributed at intervals in a 5 multiplied by 5 matrix, the plurality of fuel rods comprise 20 heating rods, 1 non-heating rod and 4 corner rods, wherein the 1 non-heating rod is positioned at the center, and the 4 corner rods are positioned at 4 corners of the matrix; positioning grids are arranged at two ends of the 25 fuel rods to fix the relative positions of the fuel rods, and heating electrodes are respectively arranged at two ends of the heating rods;
the auxiliary equipment is connected with the high-temperature heating furnace and comprises a water injection system, a gas system and a control system, wherein the water injection system is used for cooling the high-temperature heating furnace and/or submerging the cladding of the fuel rod bundle; the gas system is used for inputting or outputting gas into the high-temperature heating furnace so as to change the gas environment in the high-temperature heating furnace; the control measurement system is in communication connection with the cooling water system and the gas system to control the working states of the cooling water system and the gas system and is used for monitoring data in the high-temperature heating furnace.
In one embodiment, the outer wall of the middle cylinder is provided with two interfaces, and the two interfaces are used for being connected with an external swinging device so as to enable the high-temperature heating furnace to swing left and right.
In one embodiment, the heating rod comprises a heating part and a cladding, the cladding encapsulates the heating part, and the heating part comprises a first copper electrode, a first molybdenum electrode, a heating wire, a second molybdenum electrode and a second copper electrode which are sequentially connected from top to bottom; wherein, pile up ceramic pellet around the heater strip, there is the air gap between heating portion and the cladding.
In one embodiment, the heating part is provided with two air inlet channels, one end of each of the two air inlet channels is communicated with the air gap, and the other end of each of the two air inlet channels is communicated with the gas system; one of the air inlet channels is arranged in the first copper electrode and the first molybdenum electrode, and the other air inlet channel is arranged in the second copper electrode and the second molybdenum electrode.
In one embodiment, 1 non-heating rod is a first ring, 8 heating rods at the periphery of the non-heating rod are a second ring, and 12 heating rods at the periphery of the 8 heating rods are a third ring;
the 8 heating rods of the second ring can be filled with first inert gas through the air inlet channel, and the 12 heating rods of the third ring can be filled with second inert gas through the air inlet channel, wherein the first inert gas is different from the second inert gas.
In one embodiment, one of the corner rods is removably attached to a spacer grid that holds the fuel bundles.
In one embodiment, the heating rod further comprises a plurality of thermocouples, and one thermocouple is arranged in the non-heating rod and in the other three corner rods;
the rest thermocouples are arranged on the outer walls of the cladding of the non-heating rod and part of the heating rod, and the height positions of the thermocouples are different from each other; the thermocouple is in communication with the control measurement system.
The application also provides a method for researching the failure behavior of the nuclear reactor fuel rod bundle accident, which adopts the experimental device for researching the failure behavior of the nuclear reactor fuel rod bundle accident in any embodiment, and comprises the following steps:
checking that the experimental device is in a safe and usable state;
installing fuel bundles in 5 multiplied by 5 arrangement into a high-temperature heating furnace;
vacuumizing the high-temperature heating furnace;
swinging the high-temperature heating furnace;
electrode heating is carried out on the fuel rod bundles;
measuring data generated by the fuel bundles during heating by the control system;
all power is turned off.
In one embodiment, in the step of electrode heating the fuel bundle, further comprising,
in the heating process of the fuel rod bundle, the internal pressurization of the fuel rod bundle is carried out through a gas system;
in the constant temperature process of the fuel rod bundle, injecting water vapor into the high-temperature heating furnace through the water injection system;
after the constant temperature process of the fuel bar bundle, increasing electric power to enable the highest temperature of the fuel bar bundle to reach a preset quenching temperature;
and injecting cooling water into the high-temperature heating furnace through the water injection system at the quenching temperature of the fuel rod bundles.
In one embodiment, after all power is turned off, the steps of the experimental method for nuclear reactor fuel bundle failure behavior study further comprise:
and injecting the gel into the fuel bundles and the flow channels, and carrying out experimental offline measurement after solidification.
The experimental device for researching the accident failure behavior of the nuclear reactor fuel rod bundle has the main structure comprising a high-temperature heating furnace, and the environment of the fuel rod bundle in the high-temperature heating furnace is simulated through auxiliary equipment, so that oxidation, expansion and failure states and data of the fuel rod bundle under different environments are obtained. Specifically, the high-temperature heating furnace comprises an upper chamber, a middle cylinder body and a lower chamber, wherein coaxial channels are arranged in the upper chamber, the middle cylinder body and the lower chamber and are sequentially and detachably connected from top to bottom through flanges; the fuel rod bundle consists of a plurality of fuel rods, the fuel rod bundle penetrates through the high-temperature heating furnace along the axis of the channel, and the plurality of fuel rods are arranged in a 5 multiplied by 5 matrix and comprise 20 heating rods, 1 non-heating rod and 4 corner rods, wherein the 1 non-heating rod is positioned at the center, and the 4 corner rods are positioned at 4 corners of the matrix; the two ends of the 25 fuel bundles are provided with positioning grids for fixing the relative positions of a plurality of fuel rods, and the two ends of the fuel bundles are respectively provided with electrodes for heating the fuel bundles. The auxiliary equipment is connected with the high-temperature heating furnace and comprises a water injection system, a gas system and a control system, wherein the water injection system is used for cooling the high-temperature heating furnace and/or submerging the cladding of the fuel rod bundle; the gas system is used for inputting and outputting gas into the high-temperature heating furnace so as to change the gas environment in the high-temperature heating furnace; the control measurement system is in communication connection with the cooling water system and the gas system to control the working states of the cooling water system and the gas system and is used for monitoring data in the high-temperature heating furnace. Through the arrangement of 25 fuel rods, the application can develop the rod bundle experiment on the influence of factors such as flow channel blockage among the fuel rod bundles, rod-rod extrusion, heat radiation among the rods, axial temperature difference and the like on oxidation, expansion and failure mechanisms.
Drawings
FIG. 1 is a schematic diagram of the connection of a high temperature furnace to an accessory.
Fig. 2 is a sectional view of the high temperature heating furnace.
FIG. 3 is a cross-sectional view of a fuel bundle.
Fig. 4 is a cross-sectional view of a heating rod.
FIG. 5 is a graph of temperature change for a second ring heater rod in a fuel bundle.
Fig. 6 is a graph of the main steam and coolant flow during the quench stage.
FIG. 7 is a graph of oxide layer of a fuel bundle over time.
FIG. 8 is a graph of hydrogen leakage in a fuel bundle over time.
Fig. 9 illustrates the expansion, explosion, and fragmentation of the cladding 211 at an axial height of 400 mm.
FIG. 10 is a macro-morphology of a fuel bundle at various height locations in a second fuel bundle.
FIG. 11 is a microscopic morphology of fuel bundle cladding oxidation and cracking.
Reference numerals: a high temperature heating furnace 100; an upper chamber 110; a middle cylinder 120; an interface 121; a window 122; a lower chamber 130; fuel bundles 200; a heating rod 210; an envelope 211; a first copper electrode 212; a first molybdenum electrode 213; a heating wire 214; ceramic pellets 215; an air gap 216; an intake passage 217; a non-heating rod 220; angle bar 230; a detachable corner bar 231; fixing the angle bar 232; a water injection system 310; a steam system 321; a vacuum system 322; an inert gas system 323; thermocouple 400.
Detailed Description
In order that the above objects, features and advantages of the application will be readily understood, a more particular description of the application will be rendered by reference to the appended drawings. In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present application. The present application may be embodied in many other forms than described herein and similarly modified by those skilled in the art without departing from the spirit of the application, whereby the application is not limited to the specific embodiments disclosed below.
In the description of the present application, it should be understood that, if any, these terms "center", "longitudinal", "transverse", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc., are used herein with respect to the orientation or positional relationship shown in the drawings, these terms refer to the orientation or positional relationship for convenience of description and simplicity of description only, and do not indicate or imply that the apparatus or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore should not be construed as limiting the application.
Furthermore, the terms "first," "second," and the like, if any, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present application, the terms "plurality" and "a plurality" if any, mean at least two, such as two, three, etc., unless specifically defined otherwise.
In the present application, unless explicitly stated and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly. For example, the two parts can be fixedly connected, detachably connected or integrated; can be mechanically or electrically connected; either directly or indirectly, through intermediaries, or both, may be in communication with each other or in interaction with each other, unless expressly defined otherwise. The specific meaning of the above terms in the present application can be understood by those of ordinary skill in the art according to the specific circumstances.
In the present application, unless expressly stated or limited otherwise, the meaning of a first feature being "on" or "off" a second feature, and the like, is that the first and second features are either in direct contact or in indirect contact through an intervening medium. Moreover, a first feature being "above," "over" and "on" a second feature may be a first feature being directly above or obliquely above the second feature, or simply indicating that the first feature is level higher than the second feature. The first feature being "under", "below" and "beneath" the second feature may be the first feature being directly under or obliquely below the second feature, or simply indicating that the first feature is less level than the second feature.
It will be understood that if an element is referred to as being "fixed" or "disposed" on another element, it can be directly on the other element or intervening elements may also be present. If an element is referred to as being "connected" to another element, it can be directly connected to the other element or intervening elements may also be present. The terms "vertical," "horizontal," "upper," "lower," "left," "right," and the like as used herein, if any, are for descriptive purposes only and do not represent a unique embodiment.
Referring to fig. 1 to 4, the present application provides an experimental apparatus for accident failure behavior study of a nuclear reactor fuel bundle 200 (hereinafter referred to as experimental apparatus), wherein a main vessel is a high temperature heating furnace 100, an experimental material is a fuel bundle 200, and the experimental apparatus further comprises a plurality of auxiliary devices for simulating various environments.
Specifically, the high temperature heating furnace 100 includes an upper chamber 110, a middle cylinder 120, and a lower chamber 130, which are sequentially connected.
Referring to fig. 2, the furnace body of the high temperature heating furnace 100 is preferably made of 304 stainless steel material, and the inner wall of the heating furnace is wrapped with a heat preservation layer with the thickness of 42 mm. The heat preservation layer of the high-temperature heating furnace 100 is arranged in the furnace body and consists of an outer sleeve, the heat preservation layer and an inner container. The outer sleeve is formed by heat-resistant stainless steel plate and shaped steel assembly welding, the heat insulation layer adopts a molybdenum screen and zirconia heat preservation block combined structure, the middle barrel 120 of the high-temperature heating furnace 100 is connected with the upper chamber and the lower chamber through water cooling flanges which are formed by customizing stainless steel blind flange, the water cooling flanges form an upper furnace door and a lower furnace door of the middle barrel 120, and furnace liner heat insulation doors and water inlet and outlet guide pipes are arranged at two ends of the furnace door. The upper furnace door and the lower furnace door adopt a plurality of layers of molybdenum screen for heat preservation, and the furnace body heat preservation layer is matched with the upper furnace door and the lower furnace door heat preservation layer through bosses. The outside of the heat preservation layer in the middle cylinder 120 is cooled by water to prevent the temperature of the outer wall of the heating furnace body from being too high. The upper and lower furnace door and the middle cylinder 120 are locked by a manual hinge, and the furnace door flange and the furnace body flange are sealed and pressure-bearing by a round strip type rubber ring.
Specifically, the bottom of the lower chamber 130 is provided with a gas injection pipe and a vacuum pump, inert gas and a quenching water pipe for vacuumizing and injecting superheated steam, inert gas and quenching water in the experimental process. The top of the upper chamber 110 is provided with a vapor gas outlet for the exhaust of the experimental gas mixture. Both the upper chamber 110 and the lower chamber 130 of the high temperature heating furnace 100 are provided with cooling water inlets and outlets for electrode cooling.
The fuel bundle 200 includes a plurality of fuel rods, the fuel bundle 200 penetrating the upper chamber 110, the middle cylinder 120 and the lower chamber 130, the plurality of fuel rods being uniformly spaced in a 5×5 matrix, including 20 heating rods 210, 1 non-heating rod 220 and 4 corner rods 230, wherein the 1 non-heating rod 220 is located at the center, and the 4 corner rods 230 are located at the 4 corners of the matrix; the two ends of the 25 fuel bundles 200 are provided with positioning grids for fixing the relative positions of a plurality of fuel rods, and the two ends of the fuel bundles 200 are respectively provided with heating electrodes.
Specifically, fuel bundles 200 form a four-loop model, the arrangement of which is shown in FIG. 3. Wherein, the non-heating rods 220 are positioned at the center of the bundle (first ring), 8 heating rods 210 are arranged around the non-heating rods 220 (second ring), 12 heating rods 210 are arranged around the outer ring (third ring), and 4 zirconium alloy corner rods 230 are arranged at four corners of the outermost periphery (fourth ring). Wherein, the non-heating rods 220 located at the center of the bundle can be used to examine experimental data comparing the heating rods with the non-heating rods, and the 20 heating rods 210 located at the second and third rings can be used to simulate fuel elements of the side channels, the corner channels, and the middle channels in the stack. Four Zr alloy corner bars 230 with the diameter of 6mm are inserted into four corners of the outermost periphery, so that large-area irregular flow caused by arrangement of the heating bars 210 can be filled, and the third ring heating bars 210 are in a more uniform temperature field.
The auxiliary equipment is connected with the high-temperature heating furnace 100 and comprises a water injection system 310, a gas system and a control system. It will be appreciated that the accessory devices are all of the prior art, so the specific working principle thereof is not described, and the connection method with the high temperature heating furnace 100 and the cooperation with the high temperature heating furnace 100 are also of the prior art.
The water injection system 310 is used to cool the high temperature furnace 100 and/or flood the cladding 211 of the fuel bundle 200. Specifically, the water injection system 310 includes a cooling assembly for cooling the electrode, heating the furnace surface, and the furnace sealing flange, and a water injection assembly. The cooling water flows through each distributing pipe from the total water inlet pipe of the cooling system to each cooling part, and finally returns to the water cooler through the water return pipe. The water injection assembly mainly comprises a stainless steel water tank, a pipeline centrifugal water pump, a mass flowmeter, corresponding valves and meters. Under the experimental condition of water injection after water loss, the speed of submerged cladding 211 is controlled by a flowmeter metering mode.
The gas system includes a vapor system 321, a vacuum system 322, and an inert gas system 323. Steam generated by the steam system 321 is regulated by a valve to stably output rated flow steam, and then is metered by a vortex shedding flowmeter, and enters the high-temperature heating furnace 100 after passing through a preheating section. The vacuum system 322 is used for exhausting air in the furnace body of the high-temperature heating furnace 100 to make the vacuum degree in the furnace body lower than 1Pa. The inert gas system 323 includes a high pressure gas cylinder, pressure relief valve and corresponding valves and instrumentation to achieve an inert gas environment.
The control measurement system is in communication with the cooling water system and the gas system to control the working states of the two systems and is used for monitoring data in the high-temperature heating furnace 100, such as heating power, temperature, flow and pressure of steam, water injection flow and vacuum degree of the heating furnace, and specifically, measurement tools in the control measurement system include, but are not limited to, pressure detection meters, mass spectrometers, various flowmeters, thermocouples 400, thermometers, length measuring scales, sensors and the like, which can be determined according to different experimental requirements on the fuel bundles 200, and the control measurement system is also in the prior art.
The main structure of the experimental device for researching the accident failure behavior of the nuclear reactor fuel bundle 200 comprises a high-temperature heating furnace 100, and the environment of the fuel bundle 200 in the high-temperature heating furnace 100 is simulated through accessory equipment, so that oxidation, expansion and failure states and data of the fuel bundle 200 under different environments are obtained. Specifically, the high-temperature heating furnace 100 includes an upper chamber 110, a middle cylinder 120 and a lower chamber 130, which are all provided with coaxial channels and are sequentially detachably connected from top to bottom through flanges; the fuel bundle 200 is composed of a plurality of fuel rods, the fuel bundle 200 penetrates through the high-temperature heating furnace 100 along the axis of the channel, the plurality of fuel rods are arranged in a 5×5 matrix, and the fuel bundle comprises 20 heating rods 210, 1 non-heating rod 220 and 4 corner rods 230, wherein the 1 non-heating rod 220 is positioned at the center, and the 4 corner rods 230 are positioned at 4 corners of the matrix. The experimental system adopts the 5×5 fuel bundles 200 to arrange, and can consider the influence of four flow field channels of side channels, corner channels, middle channels and center channels on the flow and heat exchange of the fuel bundles 200. The two ends of the 25 fuel rods are provided with the positioning grids so as to fix the relative positions of the fuel rods, and the positioning grids can better simulate the larger influence on the flow heat exchange of the fuel rod bundle 200 in the actual environment, the restraining force on the fuel rod bundle 200 and the characteristics of oxidation, expansion, failure and the like of the fuel rod bundle 200.
The working pressure range of the experimental device provided by the application is 0-12MPa, the heating temperature range is room temperature to 2800 ℃, the rated heating power of each heating rod 210 reaches 20kW, the oxidation, expansion and damage experiments of the fuel rod bundles 200 under various conditions such as vacuum environment, inert gas environment, steam environment, water injection environment and the like can be realized,
referring to fig. 2, in one embodiment, the outer wall of the middle cylinder 120 is provided with two interfaces 121, and the two interfaces 121 are used for connecting with an external swing device so as to swing the high temperature heating furnace 100 from side to side.
Specifically, the external swinging device can realize +/-150 DEG inclination of the high-temperature heating furnace 100, so that experimental charging and simulated swinging experimental conditions are facilitated.
Referring to fig. 4, in one embodiment, the heating rod 210 includes a heating part and an envelope 211, the envelope 211 encapsulates the heating part, and the heating part includes a first copper electrode 212, a first molybdenum electrode 213, a heating wire 214, a second molybdenum electrode, and a second copper electrode sequentially connected from top to bottom; around the heating wire 214 are stacked ceramic pellets 215, with an air gap 216 between the heating portion and the ceramic pellets 215 and the cladding 211. The heating rod 210 has a symmetrical structure, so that only the upper half is shown in fig. 3, and the second molybdenum electrode and the second copper electrode of the lower half are not shown.
Preferably, in one embodiment, the heating of the heater rod 210 is by internal electrical heating. The heating rod 210 is heated by a butt-clamp electrode, a tantalum heating wire 214 is arranged in the center, and molybdenum electrodes are arranged at two ends for heating. The heating mode can simulate the heat transfer of an actual core block and also simulate the distribution of axial power. An air gap 216 is formed between the heating portion and the envelope 211 for containing a gas that can regulate the pressure within the envelope 211. The fuel cladding 211 is sealed with an O-ring and can move up and down at high temperatures without causing axial displacement or expansion of the bundle to die. The O-ring is pressed against the inner wall of the envelope 211 to seal the high pressure gas in the envelope 211, and in particular, the envelope 211 is made of a zirconium tube. A red copper electrode is designed above the first molybdenum electrode 213 and is used as a first copper electrode 212, a groove is formed in the red copper electrode and is used for installing a sealing ring, so that the tightness of high-pressure air in the zirconium tube is enhanced, and an inert gas heating environment is provided for the first molybdenum electrode 213 and the heating wire 214. 4O-shaped rings are arranged on the upper part and the lower part of the electrode, so that cooling water can be cooled conveniently.
Referring to fig. 4, in one embodiment, the heating portion is provided with two air inlet passages 217 (one of the air inlet passages 217 is not shown), and both of the air inlet passages 217 are in communication with the air gap 216 at one end and the gas system at the other end; one of the air inlet passages 217 is provided in the first copper electrode 212 and the first molybdenum electrode 213, and the other air inlet passage 217 is provided in the second copper electrode and the second molybdenum electrode. The gas inlet channel 217 may facilitate the gas system by injecting different gases into the second ring heater rod 210 and the third ring heater rod 210 of the fuel bundle 200, respectively, as trace gases. Specifically, in some embodiments, 8 heater rods 210 of the second ring can be injected with a first inert gas through the gas inlet channel 217, and 12 heater rods 210 of the third ring can be injected with a second inert gas through the gas inlet channel 217. Wherein the first inert gas is different from the second inert gas. For example, the first inert gas may be a gas consisting of 95% argon and 5% krypton, and the second inert gas may be helium. That is, 95% argon and 5% krypton may be injected into the second ring of heater rods 210, and helium may be injected into the third ring of heater rods 210 as a trace gas. Of course, the first inert gas and the second inert gas may be other gases, which are not limited herein. Since the gas injected into the second ring heating rod 210 and the third ring heating rod 210 are different, it is possible to determine whether or not the cladding 211 of the second ring or the third ring heating rod 210 is damaged based on the detected and excluded gas composition.
In one embodiment, one of the removable corner bars 231 is removably attached to the spacer grid to measure oxide layer growth during the experiment, and the remaining three fixed corner bars 232 are not removable.
In one embodiment, the heating rod further comprises a plurality of thermocouples 400, wherein one thermocouple 400 is arranged in the non-heating rod 220 and in the other 3 corner rods 230;
the remaining plurality of thermocouples 400 are provided on the outer walls of the envelope 211 of the non-heating rod 220 and the partial heating rod 210, and are positioned at different heights from each other.
Specifically, in the above embodiment, in order to study the temperature distribution and the differences in oxidation, expansion, and failure characteristics of the fuel bundles 200 in the radial direction and the axial direction, the thermocouples 400 are arranged at different high temperature positions of different fuel bundles 200 for measurement. Since the fuel bundle 200 has 21 heating rods 210 and non-heating rods 220 and is compact in arrangement, too many adhesion thermocouples 400 may not be laid so as not to affect the flow path. As shown in fig. 3, in the fuel bundle 200, a tungsten-rhenium thermocouple 400 is disposed inside the first ring non-heating rod 220, specifically, the material of the thermocouple 400 is tungsten-rhenium, and the thermocouples 400 are disposed at different height positions on the wall surface of the outer cladding 211; three representative rods are selected for the second ring and the third ring respectively, and thermocouples 400 are distributed at different heights Wen Weizhi for measuring the temperature distribution of the cladding 211 along the axial direction; the thermocouple 400 is arranged inside the 3 th round corner bar 230.
In one embodiment, the middle cylinder 120 is uniformly provided with 4 windows 122 along the circumferential direction, the windows 122 are quartz glass windows 122, and an infrared thermometer, a laser micrometer and a high-speed camera are arranged outside the windows 122; the infrared thermometer is used for measuring the temperature of the fuel rod bundle 200; the laser micrometer can measure the expansion process of the cladding 211 of the fuel bundle 200 under the action of the internal pressure and the high temperature in real time; the high-speed camera is used for shooting phenomena in the test process.
In addition, the infrared thermometer can also be used to observe the growth of the oxide layer on the detachable horn 231.
In order to monitor the generation rate of the combustible gas in the experimental process and judge the oxidation starting time according to the generation rate, a mass spectrometer is arranged at a steam gas outlet for gas monitoring. When the mass spectrometer detects hydrogen or carbon monoxide, or a significant step occurs in the measurement value of the thermocouple 400 on the surface of the cladding 211, the oxidation reaction can be indicated to take place, and the corresponding temperature and time are recorded and used as the starting condition of the rapid oxidation reaction of the cladding 211. The rate of overall hydrogen and carbon monoxide production by the enclosure 211 is recorded by a mass spectrometer. To monitor the position of the failure point and the failure sequence of the cladding 211 during the experiment, the second ring heater 210 was filled with 95% argon +5% krypton and the third ring heater 210 was filled with helium. When the mass spectrometer detects krypton or helium in the exhaust gas, it can be determined that the cladding 211 in the second or third ring has been broken. In addition, for each of the bottoms of the 21 jackets 211, an internal pressure detection meter is provided, when the pressure is suddenly changed, the sequence of the damage to the jackets 211 can be further determined, and the failure time, the position distribution of the failure points and the temperature of the damaged jackets 211 can be recorded.
The application also provides an experimental method for researching the accident failure behavior of the nuclear reactor fuel bundle 200, which adopts the experimental device for researching the accident failure behavior of the nuclear reactor fuel bundle 200 in any embodiment, and comprises the following steps:
the test device is checked to be in a safe and usable state. The method specifically comprises pretreatment of experimental pieces and debugging of experimental equipment. In the pretreatment of the test piece, the end surface polishing, deburring, cleaning and drying are performed on the clad 211 test piece. The 5 x 5 fuel bundle 200 and spacer grid installation is performed after the measurement and recording of the length, diameter and weight of each cladding 211 is completed. The main experimental system including heating furnace, vacuum system 322, water circulation system, steam system 321 and data acquisition system is required to be confirmed for debugging experimental equipment.
A 5×5 arrangement of fuel bundles 200 is installed into the high temperature heating furnace 100.
The high temperature heating furnace 100 is vacuumized, the inert gas system 323 is started after the vacuum degree in the furnace reaches a set value, gas is filled into the heating furnace, after the heating furnace is stabilized for a period of time, the furnace is vacuumized again and is repeated for three times, so that the oxygen content in the furnace body is removed. The oxygen content at the moment is read through an oxygen sensor at the top of the furnace body, so that only water vapor participates in oxidation reaction when a formal experiment is carried out.
The high temperature heating furnace 100 is subjected to a swing operation, and different swing amplitudes and frequencies are set for simulating ocean swing conditions.
Electrode heating of fuel bundle 200;
measuring, by the control system, data generated by the fuel bundle 200 during heating;
all power is turned off.
In one embodiment, during the step of electrode heating the fuel bundle 200, further comprising,
during the heating process of the fuel rod bundle 200, the internal pressurization of the fuel rod bundle 200 is carried out through a gas system, the rod bundle gradually increases the heating power in the steam and argon atmosphere to enable the temperature to rise from room temperature to a higher temperature (about 873K), and after the rod bundle is stabilized, the heating power is continuously gradually increased to rise to a high temperature range (1273K-1673K). In this stage, the fuel cladding 211 may have an increased internal pressure, circumferential bulge, and rod-rod extrusion, and eventually burst and release pressure.
In the constant temperature process of the fuel rod bundle 200, water vapor is injected into the high-temperature heating furnace 100 through the water injection system 310, so that the fuel rod bundle 200 enters a pre-oxidation stage, and the oxidation effect on the burning bright rod bundle in a complex environment is studied.
After the constant temperature process of the fuel rod bundle 200, increasing electric power to enable the highest temperature of the fuel rod bundle 200 to reach a preset quenching temperature;
the fuel bundles 200 are injected with cooling water into the high temperature furnace 100 through the water injection system 310 at the quenching temperature, and the highly oxidized fuel bundles 200 in this stage may undergo severe deterioration or even chipping failure under severe thermal shock.
In the reaction process of the fuel bundle 200, on-line measurement is performed, and data to be measured mainly include diameter of the cladding 211, temperature of the cladding 211 and steam, internal pressure of the cladding 211 and steam pressure, steam flow, expansion size of the cladding 211, explosion temperature and size, oxidation depth, fragmentation temperature and size, and the like.
Specifically, in the experimental online measurement, the temperature to be measured includes the temperature of the experimental section, the temperature inside the heating furnace body, the temperature of steam and cooling water, the temperature of the cladding 211 is measured by the armored tungsten-rhenium thermocouple 400 arranged on the outer surface of the cladding 211, and the thermocouple 400 is clamped on the outer wall surface of the cladding 211 tube by adopting a tantalum sheet containing zirconia for spraying; the pressure to be measured comprises the internal pressure of the heating furnace, the internal pressure of the cladding 211, a steam generator and the pressure of inert gas, wherein the internal pressure of the heating furnace and the internal pressure of the cladding 211 are monitored and collected in real time by adopting a pressure transmitter, and the pressures of the steam generator and the inert gas system 323 are measured by adopting a pressure gauge; the flow to be measured comprises steam flow, argon flow and cooling water flow, wherein the steam flow and the argon flow are measured by a turbine flowmeter, and the cooling water flow is measured by a mass flowmeter. In addition, the mass spectrometer can obtain the concentration of each component of the mixed gas in real time. When the mass spectrometer detects that krypton or helium is contained in the exhaust gas, it can be determined that the explosion of the cladding 211 occurs, and the position, temperature, and sequence of the explosion point of the cladding 211 are obtained by the internal pressure detection meter. Meanwhile, the monitoring of the real-time oxidation process of the cladding 211 can be realized through the concentration of combustible gases such as hydrogen, carbon monoxide and the like.
In one embodiment, after all power is turned off, the experimental method of the nuclear reactor fuel bundle 200 accident failure behavior study further includes the steps of:
gel is poured into the fuel bundles 200 and the flow channels, and after solidification, experimental offline measurement is performed.
Specifically, after the gel is solidified, different sections are cut along the vertical axial direction, so that the flow passage area and the blocking proportion of the flow passage at each height position when the cladding 211 is damaged are obtained, and the distribution rule of the bulge blasting positions of the cladding 211 is obtained. And then selecting the bulge and fracture area of the cladding 211, the crushing area of the cladding 211, the area near the positioning grid and the coaming, and the like to manufacture metallographic analysis samples, observing key information such as microstructure deformation characteristics, oxide layer morphology, thickness and the like of the cladding 211 in each area under SEM, and adopting EDS to analyze information such as bulge deformation of the cladding 211 tube and element component distribution and the like related to the oxide layer in the explosion area, thereby obtaining oxidation and failure rules of the fuel rod under the condition of the rod bundle.
Fig. 5 shows temperature profiles of different axial height positions of the cladding 211 of the heating rod 210 of the second ring of the fuel bundle during the operation (temperature rise, constant temperature, transient and quenching phases), in fig. 5, the vertical axis is indicated by english "temperature" and the horizontal axis is indicated by "time". The method is used for guiding the experiment to develop in real time and correcting the temperature of the cladding expansion and oxidation model in off-line measurement.
FIG. 6 shows the main steam and coolant flow curves during the quenching stage, wherein the vertical axis indicates "mass flow rate" in grams per second; the horizontal axis represents "time" in seconds. The "sequence water" in the figure means "quench water", "uncorr, for delay" means "open loop for delay".
FIG. 7 illustrates the oxide layer thicknesses measured by amperometric and microscopic detection methods at different axial height locations of the cladding 211 of the heater rod 210 of the second ring of the fuel bundle 200 for correcting the oxidation model of the cladding 211. Wherein, the English "measured by eddy-current device" means "vortex device measurement"; the english expression "metallographically determined" means "metallographic determination".
Fig. 8 shows the water vapor flow and hydrogen release rate during transient and quench phases (hydrogen is one of the major products of oxidation of the enclosure 211, the major source of hydrogen explosion during the accident phase). The hydrogen release rate increased with increasing temperature during the transient phase, but decreased rapidly with water injection during the quench phase, indicating that cooling was effective, the hydrogen release rate was used to correct the jacket oxidation model. Wherein, the English "set of cooling" means "cooling start"; the left vertical axis English is hydrogen release rate, the right numerical axis English means water vapor flow rate, the horizontal axis is time, and the units are respectively: gram per second, second.
Fig. 9 shows the expansion, explosion, and fragmentation of the cladding 211 at an axial height of 400mm for correcting the temperature limits of the explosion and fragmentation model.
FIG. 10 illustrates the flow area of the fuel bundle 200 at various axial height positions, the flow channel blockage ratio, and the offset of the cladding 211 position for correcting the blockage ratio in the expansion model of the cladding 211. Wherein bottom means lower part and top means upper part; "que" means an abbreviation for quench water.
Fig. 11 shows the oxidation growth and cracking reduction characteristics of the cladding 211 at an axial height position of 400mm, wherein english represents a picture of a certain position of the cladding 211 under the condition of injecting cooling water. Of course, other height features may be obtained.
The technical features of the above-described embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above-described embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.
The above examples illustrate only a few embodiments of the application, which are described in detail and are not to be construed as limiting the scope of the claims. It should be noted that it will be apparent to those skilled in the art that several variations and modifications can be made without departing from the spirit of the application, which are all within the scope of the application. Accordingly, the scope of protection of the present application is to be determined by the appended claims.
Claims (10)
1. An experimental set-up for the study of failure behaviour of a nuclear reactor fuel bundle, comprising:
the high-temperature heating furnace (100) comprises an upper chamber (110), a middle cylinder (120) and a lower chamber (130) which are sequentially connected;
a fuel rod bundle (200) comprising a plurality of fuel rods, wherein the fuel rod bundle (200) penetrates through the upper cavity (110), the middle cylinder (120) and the lower cavity (130), the plurality of fuel rods are uniformly distributed at intervals in a 5×5 matrix, the plurality of fuel rods comprise 20 heating rods (210), 1 non-heating rod (220) and 4 corner rods (230), 1 non-heating rod (220) is positioned at the center, and the 4 corner rods (230) are positioned at 4 corners of the matrix; heating electrodes are respectively arranged at two ends of the heating rod (210);
accessory equipment connected with the high-temperature heating furnace (100) and comprising a water injection system (310), a gas system and a control measurement system, wherein the water injection system (310) is used for cooling the high-temperature heating furnace (100) and/or submerging an enclosure (211) of the fuel rod bundle (200); the gas system is used for inputting or outputting gas into the high-temperature heating furnace (100) so as to change the gas environment in the high-temperature heating furnace (100); the control and measurement system is in communication connection with the cooling water system and the gas system to control the working states of the cooling water system and the gas system and is used for monitoring data in the high-temperature heating furnace (100).
2. The experimental device for the study of the failure behaviour of a fuel bundle of a nuclear reactor according to claim 1, characterized in that the outer wall of the central cylinder (120) is provided with two interfaces (121), said two interfaces (121) being adapted to be connected to an external rocking device for rocking the high-temperature heating furnace (100) side to side.
3. The experimental device for the investigation of the failure behaviour of a fuel bundle of a nuclear reactor according to claim 1 or 2, characterized in that the heating rod (210) comprises a heating portion and an envelope (211), the envelope (211) encapsulates the heating portion, the heating portion comprising, from top to bottom, a first copper electrode (212), a first molybdenum electrode (213), a heating wire (214), a second molybdenum electrode and a second copper electrode connected in sequence; wherein ceramic pellets (215) are stacked around the heating wire, and an air gap (216) is present between the heating portion and the cladding (211).
4. An experimental device for the study of the failure behaviour of a fuel bundle of a nuclear reactor according to claim 3, characterized in that said heating portion is provided with two inlet channels (217), both of said inlet channels (217) being in communication with said air gap (216) at one end and with said gas system at the other end; one of the air inlet channels (217) is arranged in the first copper electrode (212) and the first molybdenum electrode (213), and the other air inlet channel (217) is arranged in the second copper electrode and the second molybdenum electrode.
5. The experimental setup for the failure behavior study of a nuclear reactor fuel bundle incident according to claim 4, wherein 1 non-heating rod is a first ring, 8 heating rods on the periphery of the non-heating rod are a second ring, and 12 heating rods on the periphery of the 8 heating rods are a third ring;
the 8 heating rods of the second ring can be filled with first inert gas through the air inlet channel, and the 12 heating rods of the third ring can be filled with second inert gas through the air inlet channel, wherein the first inert gas is different from the second inert gas.
6. The experimental setup for the accident failure behavior study of a nuclear reactor fuel bundle according to claim 1, characterized in that the corner bars (230) comprise one detachable corner bar (231) and three fixed corner bars (232), wherein the detachable corner bars (231) are detachably connected with a spacer grid that fixes the fuel bundle (200).
7. The experimental setup for the failure behavior study of a nuclear reactor fuel bundle incident according to claim 6, further comprising a plurality of thermocouples (400),
the thermocouple (400) is arranged in the non-heating rod (220) and in the fixed angle rod (232);
the rest of the thermocouples (400) are arranged on the outer walls of the cladding (211) of the non-heating rod (220) and part of the heating rod (210) and have different height positions; the thermocouple (400) is in communication with the control measurement system.
8. A method for studying the failure behavior of a nuclear reactor fuel bundle accident, using the experimental device for studying the failure behavior of a nuclear reactor fuel bundle accident as set forth in claims 1 to 7, comprising the steps of:
checking that the experimental device is in a safe and usable state;
-installing the fuel bundles (200) in a 5 x 5 arrangement into the high temperature furnace (100);
vacuumizing the high-temperature heating furnace (100);
performing a swing operation on the high-temperature heating furnace (100);
-electrode heating the fuel bundle (200);
measuring, by a control system, data generated by the fuel bundles (200) during heating;
all power is turned off.
9. The method of claim 8, wherein the method of performing a nuclear reactor fuel bundle failure behavior study,
in the step of electrode heating the fuel bundle (200), further comprising,
the fuel rod bundle (200) is internally pressurized by a gas system during the temperature rising process;
the fuel rod bundles (200) inject water vapor into the high-temperature heating furnace (100) through a water injection system (310) in the constant temperature process;
after the constant temperature process of the fuel rod bundle (200), increasing electric power to enable the highest temperature of the fuel rod bundle (200) to reach a preset quenching temperature;
the fuel rod bundle (200) is injected with cooling water into the high-temperature heating furnace (100) through a water injection system (310) at the quenching temperature.
10. The method of nuclear reactor fuel bundle failure behavior research of claim 9, wherein the step of experimental method of nuclear reactor fuel bundle failure behavior research after turning off all power further comprises:
and (3) pouring gel into the fuel rod bundles (200) and the flow channels, and carrying out experimental offline measurement after solidification.
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