CN117571387A - Off-line sipping sampling device and sampling method for radioactive assembly - Google Patents
Off-line sipping sampling device and sampling method for radioactive assembly Download PDFInfo
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- CN117571387A CN117571387A CN202311513387.6A CN202311513387A CN117571387A CN 117571387 A CN117571387 A CN 117571387A CN 202311513387 A CN202311513387 A CN 202311513387A CN 117571387 A CN117571387 A CN 117571387A
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- 238000005070 sampling Methods 0.000 title claims abstract description 139
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 110
- 238000000034 method Methods 0.000 title claims abstract description 17
- 238000002791 soaking Methods 0.000 claims abstract description 109
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 85
- 230000007704 transition Effects 0.000 claims abstract description 48
- 239000007788 liquid Substances 0.000 claims abstract description 21
- 238000001802 infusion Methods 0.000 claims abstract description 11
- 230000001502 supplementing effect Effects 0.000 claims description 17
- 238000007599 discharging Methods 0.000 claims description 12
- 238000011010 flushing procedure Methods 0.000 claims description 8
- 238000007789 sealing Methods 0.000 claims description 7
- 239000002699 waste material Substances 0.000 claims description 7
- 239000002351 wastewater Substances 0.000 claims description 5
- 230000009471 action Effects 0.000 claims description 4
- 238000011049 filling Methods 0.000 claims description 3
- 238000004891 communication Methods 0.000 claims description 2
- 238000001514 detection method Methods 0.000 abstract description 15
- 239000003758 nuclear fuel Substances 0.000 abstract description 2
- 239000007789 gas Substances 0.000 description 21
- 230000006378 damage Effects 0.000 description 19
- 239000012857 radioactive material Substances 0.000 description 4
- 208000027418 Wounds and injury Diseases 0.000 description 3
- 238000000605 extraction Methods 0.000 description 3
- 208000014674 injury Diseases 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 238000005086 pumping Methods 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 239000013589 supplement Substances 0.000 description 2
- 230000006978 adaptation Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000011033 desalting Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000010992 reflux Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000003756 stirring Methods 0.000 description 1
- 239000002912 waste gas Substances 0.000 description 1
Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/10—Devices for withdrawing samples in the liquid or fluent state
- G01N1/14—Suction devices, e.g. pumps; Ejector devices
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- General Physics & Mathematics (AREA)
- Immunology (AREA)
- Pathology (AREA)
- Sampling And Sample Adjustment (AREA)
Abstract
The invention relates to the technical field of nuclear fuel element detection, in particular to an off-line sipping sampling device and a sampling method of a radioactive assembly, wherein the sampling device comprises: an infusion container for infusing the radioactive assembly; the water inlet interface of the self-priming pump is connected with the soaking container, the water inlet interface is connected with a pump inlet valve in series, the water outlet interface of the self-priming pump is connected with a pump outlet valve and a flowmeter in series in sequence, and the outlet of the flowmeter is connected with the soaking container; the sampling bottle is connected with a pipeline connecting the soaking container and the flowmeter through a sampling valve; the upper box body is used for accommodating the sampling bottle, and the side wall of the upper box body is provided with operation gloves; the transition box can be communicated with the upper box body through a movable door, and is provided with a sampling door in a matching mode; the sampling device can take offline sip sampling of the liquid of the radioactive assembly. The sampling method is based on the aforementioned sampling device.
Description
Technical Field
The invention relates to the technical field of nuclear fuel element detection, in particular to an off-line sipping sample device of a radioactive assembly and a sampling method.
Background
The radioactive assembly is an assembly consistent with the structure of a control rod assembly of a nuclear power plant, and in order to verify whether an enclosure of the assembly is damaged after irradiation, the assembly needs to be subjected to damage inspection. The breakage of the radioactive assembly can only be determined by analyzing the radionuclide content of the liquid medium. At present, sip detection of irradiated fuel assemblies is commonly applied in nuclear power plants and research stacks at home and abroad, but off-line sip detection is an efficient damage detection method, and the basic principle is that irradiated equipment is stored in a closed container for a period of time, then a liquid medium in the closed container is taken out, and whether damage occurs or not and the size of a damage notch is analyzed are judged by analyzing the content of radioactive nuclides in the liquid medium. Most use off-line or on-line detection of water insoluble Xe133 and Kr85, but no off-line sipping of the liquid against the radioactive assembly.
Disclosure of Invention
The invention provides an offline sip sampling device and a sampling method for a radioactive assembly, which can carry out offline sip sampling on liquid for soaking the radioactive assembly so as to detect the damage of the radioactive assembly and solve the difficult problem of damage detection of the radioactive assembly.
The invention is realized by the following technical scheme:
in a first aspect, the present invention provides an offline sip-like device for a radioactive assembly, comprising: an infusion container for infusing the radioactive assembly; the water inlet interface of the self-priming pump is connected with the soaking container, the water inlet interface is connected with a pump inlet valve in series, the water outlet interface of the self-priming pump is connected with a pump outlet valve and a flowmeter in series in sequence, and the outlet of the flowmeter is connected with the soaking container; the sampling bottle is connected with a pipeline connecting the soaking container and the flowmeter through a sampling valve; the upper box body is used for accommodating the sampling bottle, and the side wall of the upper box body is provided with operation gloves; the transition box can be communicated with the upper box body through a movable door, and is provided with a sampling door in a matching mode; the sampling bottle can be moved from the upper box body to the transition box body through the operation glove.
The radioactive assembly offline sipping sample absorbing device is provided with the soaking container and the self-priming pump, the radioactive assembly is soaked by the soaking container, under the condition that the radioactive assembly is damaged, radionuclides can enter liquid in the soaking container, a water inlet interface of the self-priming pump is connected with the soaking container, a pump inlet valve and a water outlet interface are connected in series in sequence, a pump outlet valve and a flowmeter are connected in series with the water inlet interface, an outlet of the flowmeter is connected with the soaking container, under the condition that the pump inlet valve and the pump outlet valve are closed, the radioactive assembly is enabled to be stationary in the soaking container, under the condition that the self-priming pump, the pump inlet valve and the pump outlet valve are opened, desalted water in the soaking container can be fully stirred, so that radioactive substances which possibly overflow can be uniformly mixed in the solution, meanwhile, a sampling bottle is connected with a pipeline connecting the soaking container and the flowmeter by a sampling valve, at the moment, sampling can be carried out by opening the sampling valve, and after sampling is finished, the self-priming pump, the pump inlet valve and the pump outlet valve are closed.
Wherein, can observe the flow that gets into the liquid flow through the flowmeter, and the sample bottle is in last box, go up the box lateral wall be provided with operation gloves, transition case can through the dodge gate with go up box intercommunication, transition case adaptation have the sample door to can remove the sample bottle from last box in to the transition incasement through operation gloves, make the sample bottle can enter into sealed transition incasement, and through the mode to transition case extraction vacuum, in time with radioactive gas's emission, then open the transition case and take out the sample bottle, avoided radioactive gas to cause the injury to operating personnel and environment.
In conclusion, the offline sip-absorbing sample device for the radioactive assembly provided by the invention is convenient for detecting the damage of the radioactive assembly, and solves the difficult problem of damage detection of the radioactive assembly.
In an alternative embodiment, the device further comprises a lower box body, wherein the soaking container and the self-priming pump are arranged in the lower box body, so that radiation protection treatment is carried out on the soaking container and the self-priming pump through the lower box body.
In an alternative embodiment, the device further comprises a vacuum pump for pumping the transition box so as to pump the waste gas in the transition box and the upper box and avoid the escape of radioactive gas.
In an alternative embodiment, the sliding door is adapted with a rack, a gear capable of rotating along the axis of the transition box is arranged in the transition box, and the rack is driven by rotation of the gear to open the sliding door, so that the sliding door is driven to be opened or closed by a hand wheel.
In an alternative embodiment, the upper end of the soaking container is provided with an exhaust valve, and the outlet of the exhaust valve is communicated with the inner cavity of the upper box body; the soaking container is connected with a water supplementing valve between the soaking container and the pump inlet valve, and an inlet of the water supplementing valve is used for being connected with a desalting water system so as to supplement the soaking container and wash the sampling back after the sampling is completed.
In an alternative embodiment, the soaking vessel is independently provided with four to facilitate breakage detection of four sets of radioactive assemblies simultaneously.
In a second aspect, the invention provides an offline sip-like method for a radioactive assembly, based on the offline sip-like device, comprising the steps of:
s10, placing the radioactive assembly into a soaking container;
s20, opening a pump inlet valve, starting a self-priming pump, and gradually opening a pump outlet valve;
s30, after the flow of the self-priming pump is stable, closing a sealing cover of the soaking container to enable the soaking container and a system pipeline to be filled with water;
s40, closing the self-priming pump, the pump inlet valve and the pump outlet valve;
s50, after the radioactive assembly is soaked in the soaking container for a first set time, starting the self-priming pump, opening the pump inlet valve and the pump outlet valve, and operating for a second set time;
s60, opening a sampling valve to sample, and sequentially closing the sampling valve, the self-priming pump, the pump inlet valve and the pump outlet valve after the sampling is finished.
The radioactive assembly offline sipping sample absorbing method provided by the invention is based on the radioactive assembly offline sipping sample absorbing device, firstly, the radioactive assembly is placed into a soaking container, then a pump inlet valve is opened, a self-priming pump is started, a pump outlet valve is gradually opened, after the flow rate of the self-priming pump is stable, a sealing cover of the soaking container is closed, the soaking container and a system pipeline are filled with water, then the self-priming pump, the pump inlet valve and the pump outlet valve are closed, the radioactive assembly is statically soaked in the container, after the radioactive assembly is soaked in the soaking container for a first set time, the self-priming pump is started, the pump inlet valve and the pump outlet valve are opened, a second set time is operated, desalted water in the soaking container is fully stirred, so that radioactive materials which possibly overflow are even, then the sampling valve is opened for sampling, after the sampling is finished, the sampling valve, the self-priming pump, the pump inlet valve and the pump outlet valve are sequentially closed, and the taken out valve are analyzed, and whether the radioactive assembly is damaged or not can be judged. Therefore, the damage of the radioactive assembly is conveniently detected, and the difficult problem of damage detection of the radioactive assembly is solved.
Specifically, S60 includes the steps of:
s61, sampling by holding a sampling bottle through an operation glove;
s62, placing the sampling bottle in a transition box of the sampling device;
s63, the movable door is lowered under the action of the gear and the rack, so that the transition box is closed;
s64, starting a vacuum pump, and discharging the gas in the transition box to a radioactive gas treatment system of the nuclear power plant;
s65, opening the sampling door, and taking out the sampling bottle.
This can prevent the radioactive gas from leaking out and damaging the environment and personnel.
In an alternative embodiment, the method further comprises the step of S70, replenishing the soaking container after sampling more than 3 times or when the liquid level in the soaking container is lower than the water outlet;
wherein S70 comprises the steps of:
s71, closing a pump inlet valve and a pump outlet valve, and sequentially opening an exhaust valve, a water supplementing valve and a water inlet valve;
s72, opening a valve of a demineralized water system of the nuclear power plant, and supplementing water to the soaking container;
s73, discharging exhaust gas in the soaking container to a sampling box of a sampling device, opening a vacuum pump of the sampling device, and discharging exhaust gas to a radioactive gas treatment system of the nuclear power plant;
and S74, after the exhaust pipeline discharges water, the exhaust valve, the water supplementing valve, the water inlet valve and the vacuum pump are sequentially closed.
Thereby timely replenishing the soaking container with demineralized water.
In an alternative embodiment, the method further comprises a flushing step S80, after the sampling device is used for the first time, flushing the sampling circuit;
wherein S80 comprises the steps of:
s81, closing the soaking container, opening a pump inlet valve, a pump outlet valve and an exhaust valve, and starting a self-priming pump to pump all water in the soaking container into the upper box body;
s82, discharging the waste liquid in the upper box body to a waste water tank through a waste liquid discharge interface;
s83, filling the soaking container with non-radioactive desalted water by adopting S70.
Thereby ensuring the accuracy of the subsequent detection.
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. the radioactive assembly offline sipping sample absorbing device is provided with the soaking container and the self-priming pump, the radioactive assembly is soaked by the soaking container, under the condition that the radioactive assembly is damaged, radionuclides can enter liquid in the soaking container, a water inlet interface of the self-priming pump is connected with the soaking container, a pump inlet valve and a pump outlet valve and a flowmeter are sequentially connected in series with the water inlet interface, an outlet of the flowmeter is connected with the soaking container, under the condition that the pump inlet valve and the pump outlet valve are closed, the radioactive assembly is enabled to be stationary in the soaking container, under the condition that the self-priming pump, the pump inlet valve and the pump outlet valve are opened, desalted water in the soaking container can be fully stirred, so that radioactive substances possibly overflowed into the solution can be uniformly mixed, meanwhile, a sampling bottle is connected with a pipeline connecting the soaking container and the flowmeter by a sampling valve, sampling can be carried out by opening the sampling valve, after the sampling is completed, the self-priming pump, the pump inlet valve and the pump outlet valve are closed, and the pump outlet valve are sequentially connected in series, so that the radioactive assembly is convenient to detect damage of the radioactive assembly, and the problem of detecting radioactive assembly is solved.
2. The invention provides an offline sipping sampling device for a radioactive assembly, wherein a sampling bottle is arranged in an upper box body, an operation glove is arranged on the side wall of the upper box body, a transition box is communicated with the upper box body through a movable door, the transition box is provided with a sampling door in an adapting mode, and the sampling bottle can be moved into the transition box from the upper box body through the operation glove, so that the sampling bottle can enter the sealed transition box, radioactive gas is discharged in time in a vacuum mode of the transition box, and then the transition box is opened to take out the sampling bottle, thereby avoiding the injury of the radioactive gas to operators and the environment.
3. The radioactive assembly offline sipping sample absorbing method provided by the invention is based on the radioactive assembly offline sipping sample absorbing device, firstly, the radioactive assembly is placed into a soaking container, then a pump inlet valve is opened, a self-priming pump is started, a pump outlet valve is gradually opened, after the flow of the self-priming pump is stable, a sealing cover of the soaking container is closed, so that the soaking container and a system pipeline are filled with water, then the self-priming pump, the pump inlet valve and the pump outlet valve are closed, the radioactive assembly is statically soaked in the container, after the radioactive assembly is soaked in the soaking container for a first set time, the self-priming pump is started, the pump inlet valve and the pump outlet valve are opened, and a second set time is operated, so that desalted water in the soaking container is fully stirred, radioactive materials which possibly overflow are even, then the sampling valve is opened for sampling, and after the sampling is finished, the sampling valve, the self-priming pump, the pump inlet valve and the pump outlet valve are sequentially closed, and the pump outlet valve are analyzed, so that whether the radioactive assembly is damaged or not can be judged.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the embodiments will be briefly described below, it being understood that the following drawings only illustrate some embodiments of the present invention and therefore should not be considered as limiting the scope, and other related drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
In the drawings:
FIG. 1 is a schematic view of a front axial structure of an off-line sip-like device of a radioactive assembly according to an embodiment of the present invention;
FIG. 2 is a schematic view of a rear axle measurement structure of the radioactive assembly according to the embodiment of the present invention, with the rear case plate removed;
FIG. 3 is a schematic diagram of the piping of the offline sip-like device of the radioactive assembly according to the embodiment of the present invention.
In the drawings:
the device comprises a 1-upper box body, a 2-lifting ring, a 3-control box, a 4-sampling water outlet pipe, a 5-sampling bottle, a 6-operation glove, a 7-lower box body, 8-pulleys, 9-fixed supports, a 10-transition box, an 11-hand wheel, a 12-gear, a 13-rack, a 14-rotary switch, a 15-sampling door, a 16-moving door, a 17-inlet pipe, an 18-vacuum pump, a 19-exhaust valve, a 20-sampling valve, a 21-pump outlet valve, a 22-flowmeter, a 23-self-priming pump, a 24-pump inlet valve, a 25-water supplementing valve, a 26-water inlet valve, a 27-water supplementing interface, a 28-water inlet interface, a 29-water outlet interface, a 30-waste liquid discharge interface and a 31-soaking container.
Detailed Description
For the purpose of making the objects, technical solutions and advantages of the embodiments of the present invention more apparent, the technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention, and it is apparent that the described embodiments are some embodiments of the present invention, but not all embodiments of the present invention. The components of the embodiments of the present invention generally described and illustrated in the figures herein may be arranged and designed in a wide variety of different configurations.
It should be noted that: like reference numerals and letters denote like items in the following figures, and thus once an item is defined in one figure, no further definition or explanation thereof is necessary in the following figures. Embodiments of the invention and features of the embodiments may be combined with each other without conflict.
In the description of the embodiments of the present invention, the terms "center", "upper", "lower", "left", "right", "vertical", "longitudinal", "lateral", "horizontal", "inner", "outer", "front", "rear", "top", "bottom", etc. indicate orientations or positional relationships based on those shown in the drawings, or those conventionally put in use of the product of the application, or those conventionally understood by those skilled in the art, are merely for convenience of description and simplicity of description, and do not indicate or imply that the apparatus or elements referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present invention.
In the description of the present invention, unless explicitly stated and limited otherwise, the terms "disposed," "mounted," "connected," "coupled," and "connected" are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention will be understood in specific cases by those of ordinary skill in the art.
Example 1
With reference to FIGS. 1-3, the present embodiment provides an offline sipping sample device of a radioactive assembly, comprising: an infusion container 31, said infusion container 31 for infusing the radioactive assembly; the self-priming pump 23, the water inlet interface 28 of the self-priming pump 23 is connected with the soaking container 31, the water inlet interface 28 is connected with the pump inlet valve 24 in series, the water outlet interface 29 of the self-priming pump 23 is connected with the pump outlet valve 21 and the flowmeter 22 in series in sequence, and the outlet of the flowmeter 22 is connected with the soaking container 31; a sampling bottle 5, wherein the sampling bottle 5 is connected with a pipeline connecting the soaking container 31 and the flowmeter 22 through a sampling valve 20; the upper box body 1 is used for accommodating a sampling bottle 5, and the side wall of the upper box body 1 is provided with an operation glove 6; a transition box 10, said transition box 10 being capable of communicating with said upper box 1 through a mobile door 16, said transition box 10 being fitted with a sampling door 15; wherein the sampling bottle 5 can be moved from the upper case 1 into the transition case 10 by the operating glove 6.
In this embodiment, a vacuum pump 18 is further included, and the vacuum pump 18 is used for pumping the transition box 10, so as to pump the exhaust gas in the transition box 10 and the upper box body 1, and avoid the escape of radioactive gas.
Referring again to fig. 1, specifically, the sliding door 16 is fitted with a rack 13, a gear 12 capable of rotating along its own axis is disposed in the transition box 10, and the sliding door 16 can be opened by rotating the gear 12 to drive the rack 13, so that the sliding door 16 can be opened or closed by driving the hand wheel 11.
On the basis, the upper end of the soaking container 31 is provided with an exhaust valve 19, and the outlet of the exhaust valve 19 is communicated with the inner cavity of the upper box body 1; a water supplementing valve 25 is connected between the soaking container 31 and the pump inlet valve 24, and an inlet of the water supplementing valve 25 is used for being connected with a demineralized water system so as to supplement the soaking container 31 and wash back the sample after the sample is taken.
It should be understood that this embodiment further includes a lower case 7, and the soaking vessel 31 and the self-priming pump 23 are both installed in the lower case 7 to perform radiation-proof treatment on the soaking vessel 31 and the self-priming pump 23 through the lower case 7.
In connection with fig. 3, the soaking vessel 31 is independently provided with four, i.e. four sampling circuits simultaneously, so as to detect the breakage of four sets of radioactive components simultaneously.
It should be noted that, the radioactive assembly offline sample sucking device provided in this embodiment is used for soaking the radioactive assembly through the soaking container 31, under the condition that the radioactive assembly is damaged, the radionuclide can enter the liquid in the soaking container 31, the water inlet 28 of the self-priming pump 23 is connected with the soaking container 31, the water inlet 28 is connected with the pump inlet valve 24 and the water outlet 29 in series, the pump outlet valve 21 and the flowmeter 22 are connected with the soaking container 31 in series in sequence, the outlet of the flowmeter 22 is connected with the soaking container 31, under the condition that the pump inlet valve 24 and the pump outlet valve 21 are closed, the radioactive assembly is still in the soaking container 31, under the condition that the self-priming pump 23, the pump inlet valve 24 and the pump outlet valve 21 are opened, the desalted water in the soaking container 31 can be fully stirred, so that the radioactive materials possibly overflowed are uniformly mixed in the solution, meanwhile, the sampling bottle 5 is connected with the pipeline connecting the soaking container 31 and the flowmeter 22 through the sampling valve 20, at this time, the sampling valve 20 is opened, and the self-priming pump 23, the pump inlet valve 24 and the pump outlet valve 21 can be closed after the sampling is completed.
Wherein, can observe the flow that gets into the liquid flow through flowmeter 22, and sample bottle 5 is in last box 1, go up box 1 lateral wall be provided with operation gloves 6, transition case 10 can through the dodge gate 16 with go up box 1 intercommunication, transition case 10 is adapted with sample gate 15, and can follow last box 1 with sample bottle 5 and remove to in the transition case 10 through operation gloves 6, make sample bottle 5 can enter into sealed transition case 10, and through the mode to transition case 10 extraction vacuum, in time discharge radioactive gas, then open transition case 10 and take out sample bottle 5, avoided radioactive gas to cause the injury to operating personnel and environment.
In summary, the offline sampling device for the radioactive assembly provided by the embodiment is convenient for detecting the damage of the radioactive assembly, and solves the difficult problem of damage detection of the radioactive assembly.
Example 2
The present embodiment provides an offline sip-like method for a radioactive assembly, based on embodiment 1, the described offline sip-like device for a radioactive assembly includes the following steps:
s10, placing the radioactive assembly into a soaking container 31.
Specifically, before sampling is started, a crane or other hoisting equipment is used to connect the hoisting ring 2 of the sampling device, the sampling device is placed at a corresponding position, then the sampling device is pushed, the sampling device is moved to a designated position under the action of the pulley 8 at the lower part of the sampling device, and the fixed support 9 at the lower part of the sampling device is rotated to fix the sampling device.
After the whole part of the sampling device is fixed, a metal hose is used for connecting the water inlet port 28 of the self-priming pump 23 with the outlet of the soaking container 31, the water outlet port 29 of the self-priming pump 23 with the inlet of the soaking container 31, the exhaust valve 19 with the exhaust port of the soaking container 31, and finally a special tool is used for placing the radioactive component into the soaking container 31.
S20, opening a pump inlet valve 24, starting a self-priming pump 23, and gradually opening a pump outlet valve 21.
Specifically, after confirming that each valve state is correct, the self-priming pump 23 is restarted, and the pump outlet valve 21 is slowly opened.
S30, after the flow of the self-priming pump 23 is stable, the sealing cover of the soaking container 31 is closed, so that the soaking container 31 and the system pipeline are filled with water. That is, by observing the state of the flowmeter 22 in the sampling circuit, the seal cap of the soaking vessel 31 is closed after the reflux flow rate is stabilized.
S40, the self-priming pump 23, the pump inlet valve 24, and the pump outlet valve 21 are closed.
S50, after the radioactive assembly is soaked in the soaking container 31 for a first set time, the self-priming pump 23 is started, the pump inlet valve 24 and the pump outlet valve 21 are opened, and a second set time is operated.
That is, after the radioactive assembly is soaked in the soaking container 31 for a certain period of time, the self-priming pump 23 is started, and the self-priming pump 23 is operated for a second set period of time (10 min in the present embodiment) to stir the water in the soaking container 31 uniformly.
S60, opening the sampling valve 20 to sample, and sequentially closing the sampling valve 20, the self-priming pump 23, the pump inlet valve 24 and the pump outlet valve 21 after the sampling is finished.
Specifically, S60 includes the sub-steps of:
s61, sampling the sample bottle 5 by holding the operation glove 6, namely 1) the operator holds the sample bottle 5 by holding the operation glove 6;
s62, placing the sampling bottle 5 in the transition box 10 of the sampling device, namely, placing the sampling bottle 5 in the transition box 10 by using the operation glove 6;
s63, the movable door 16 is lowered under the action of the gear 12 and the rack 13, so that the transition box 10 is closed;
s64, starting the vacuum pump 18, and discharging the gas in the transition box 10 to a radioactive gas treatment system of the nuclear power plant, wherein the time for starting the vacuum pump 18 this time is 2 minutes in the embodiment;
s65, opening the sampling door 15, taking out the sampling bottle 5, namely, screwing the rotary switch 14 to open the sampling door 15 after the air extraction is completed, and taking out the sampling bottle 5 to complete single sampling, thereby preventing the radioactive gas from leaking to cause damage to the environment and personnel.
Typically, sampling is performed every 8 hours, and the number of times of sampling is not less than 6 times; after the sampling is completed, the water sample is analyzed, and whether the radioactive assembly is damaged can be judged through comparison. And (3) after the sampling is completed, all the equipment in the sampling device is restored to the original state.
Wherein, after sampling for more than 3 times or when the liquid level in the soaking container 31 is lower than the water outlet, the soaking container 31 needs to be supplemented with water, which comprises the following specific steps:
s71, closing the pump inlet valve 24 and the pump outlet valve 21, and sequentially opening the exhaust valve 19, the water supplementing valve 25 and the water inlet valve 26;
s72, opening a valve of a demineralized water system of the nuclear power plant, and supplementing water to the soaking container 31;
s73, discharging the exhaust gas in the soaking container 31 to a sampling box of a sampling device, opening a vacuum pump 18 of the sampling device, and discharging the exhaust gas to a radioactive gas treatment system of the nuclear power plant;
and S74, after the exhaust pipeline discharges water, the exhaust valve 19, the water supplementing valve 25, the water inlet valve 26 and the vacuum pump 18 are sequentially closed, and the water entering the upper box body 1 is discharged into a wastewater pool of the nuclear power plant through the wastewater discharge interface 30.
It should be understood that after the offline sip detection device is used for the first time, for the accuracy of the subsequent detection, the device and the sampling circuit in the system need to be flushed, and the specific flushing steps are as follows:
s81, closing the soaking container 31, opening the pump inlet valve 24, the pump outlet valve 21 and the exhaust valve 19, and starting the self-priming pump 23 to pump all the water in the soaking container 31 into the upper box body 1; the radioactive assembly placed in the soaking container 31 is taken out, and the sealing cover of the soaking container 31 is closed;
s82, discharging the waste liquid in the upper box body 1 to a waste water tank through the waste liquid discharge interface 30;
s83, filling the soaking container 31 with non-radioactive desalted water by adopting S70, flushing for a certain time, sampling and analyzing, and repeating the flushing step until the analysis result reaches a specified value if the analysis result is unqualified, so as to finish flushing the system and restore the system state.
In summary, in the offline sip sample sucking method for a radioactive assembly provided in this embodiment, based on the offline sip sample sucking device for a radioactive assembly described in embodiment 1, firstly, the radioactive assembly is placed into a soaking container 31, then a pump inlet valve 24 is opened, a self-priming pump 23 is started, and a pump outlet valve 21 is gradually opened, after the flow rate of the self-priming pump 23 is stable, a sealing cover of the soaking container 31 is closed, so that the soaking container 31 and a system pipeline are filled with water, then the self-priming pump 23, the pump inlet valve 24 and the pump outlet valve 21 are closed, so that the radioactive assembly is statically soaked in the container, after the radioactive assembly is soaked in the soaking container 31 for a first set time, the self-priming pump 23, the pump inlet valve 24 and the pump outlet valve 21 are started, and a second set time is operated, desalted water in the soaking container 31 is fully stirred, so that possibly overflowed radioactive materials are uniform, then the sampling valve 20 is opened to sample the sampling, and after the sampling is finished, the sampling valve 20, the self-priming pump 23, the pump inlet valve 24 and the pump outlet valve 21 are sequentially closed, and whether the taken out radioactive assembly is analyzed. Therefore, the damage of the radioactive assembly is conveniently detected, and the difficult problem of damage detection of the radioactive assembly is solved.
The foregoing description of the embodiments has been provided for the purpose of illustrating the general principles of the invention, and is not meant to limit the scope of the invention, but to limit the invention to the particular embodiments, and any modifications, equivalents, improvements, etc. that fall within the spirit and principles of the invention are intended to be included within the scope of the invention.
Claims (10)
1. A radioactive assembly off-line sipping sample device, comprising:
an infusion container (31), the infusion container (31) for infusing a radioactive assembly;
the self-priming pump (23), a water inlet interface (28) of the self-priming pump (23) is connected with the soaking container (31), a pump inlet valve (24) is connected in series with the water inlet interface (28), a pump outlet valve (21) and a flowmeter (22) are connected in series with a water outlet interface (29) of the self-priming pump (23) in sequence, and an outlet of the flowmeter (22) is connected with the soaking container (31);
a sampling bottle (5), wherein the sampling bottle (5) is connected with a pipeline connecting the soaking container (31) and the flowmeter (22) through a sampling valve (20);
the upper box body (1), wherein the upper box body (1) is used for accommodating a sampling bottle (5), and the side wall of the upper box body (1) is provided with operating gloves (6);
a transition box (10), wherein the transition box (10) can be communicated with the upper box body (1) through a movable door (16), and the transition box (10) is adapted with a sampling door (15);
wherein, can move the sample bottle (5) from in last box (1) to in transition case (10) through operating gloves (6).
2. The offline sip-like device of the radioactive assembly according to claim 1, characterized in that it further comprises a lower box (7), said infusion container (31) and said self-priming pump (23) being both mounted inside said lower box (7).
3. The offline sip-like device of the radioactive assembly according to claim 1, characterized in that it further comprises a vacuum pump (18), said vacuum pump (18) being used for evacuating the transition box (10).
4. The offline sip-like device of the radioactive assembly according to claim 1, characterized in that the mobile door (16) is fitted with a rack (13), a gear (12) capable of rotating along its own axis is arranged inside the transition box (10), and the mobile door (16) can be opened by driving the rack (13) through the rotation of the gear (12).
5. The offline sipping device of the radioactive assembly according to any of the claims from 1 to 4, characterized in that the upper end of the infusion container (31) is provided with an exhaust valve (19), the outlet of the exhaust valve (19) being in communication with the inner cavity of the upper box (1);
a water supplementing valve (25) is connected between the soaking container (31) and the pump inlet valve (24), and an inlet of the water supplementing valve (25) is used for being connected with a demineralized water system.
6. The offline sip-like device of the radioactive assembly according to claim 5, characterized in that the infusion container (31) is provided with four independently.
7. A radioactive assembly offline sipping method based on the radioactive assembly offline sipping device of claim 5, comprising the steps of:
s10, placing the radioactive assembly into a soaking container (31);
s20, opening a pump inlet valve (24), starting a self-priming pump (23), and gradually opening a pump outlet valve (21);
s30, after the flow of the self-priming pump (23) is stable, closing a sealing cover of the soaking container (31) to enable the soaking container (31) and a system pipeline to be filled with water;
s40, closing the self-priming pump (23), the pump inlet valve (24) and the pump outlet valve (21);
s50, after the radioactive assembly is soaked in the soaking container (31) for a first set time, starting the self-priming pump (23), opening the pump inlet valve (24) and the pump outlet valve (21), and operating for a second set time;
s60, opening a sampling valve (20) for sampling, and sequentially closing the sampling valve (20), a self-priming pump (23), a pump inlet valve (24) and a pump outlet valve (21) after the sampling is finished.
8. The offline sip-like method of the radioactive assembly according to claim 7, characterized in that S60 comprises the steps of:
s61, sampling by holding the sampling bottle (5) through the operation glove (6);
s62, placing the sampling bottle (5) in a transition box (10) of the sampling device;
s63, the movable door (16) is lowered under the action of the gear (12) and the rack (13), so that the transition box (10) is closed;
s64, starting a vacuum pump (18), and discharging the gas in the transition box (10) to a radioactive gas treatment system of the nuclear power plant;
s65, opening the sampling door (15), and taking out the sampling bottle (5).
9. The offline sip method of the radioactive assembly according to claim 7, characterized in that it further comprises the step S70 of replenishing the infusion container (31) after sampling more than 3 times or when the liquid level in the infusion container (31) is to be lower than the water outlet;
wherein S70 comprises the steps of:
s71, closing a pump inlet valve (24) and a pump outlet valve (21), and sequentially opening an exhaust valve (19), a water supplementing valve (25) and a water inlet valve (26);
s72, opening a valve of a demineralized water system of the nuclear power plant, and supplementing water to the soaking container (31);
s73, discharging exhaust gas in the soaking container (31) to a sampling box of a sampling device, opening a vacuum pump (18) of the sampling device, and discharging exhaust gas to a radioactive gas treatment system of the nuclear power plant;
and S74, after the exhaust pipeline discharges water, sequentially closing the exhaust valve (19), the water supplementing valve (25), the water inlet valve (26) and the vacuum pump (18).
10. The method according to claim 7, further comprising a flushing step S80 of flushing the sampling circuit after the sampling device is first used;
wherein S80 comprises the steps of:
s81, closing the soaking container (31), opening a pump inlet valve (24), a pump outlet valve (21) and an exhaust valve (19), and starting a self-priming pump (23) to pump all water in the soaking container (31) into the upper box body (1);
s82, discharging the waste liquid in the upper box body (1) to a waste water tank through a waste liquid discharge interface (30);
s83, filling the soaking container (31) with non-radioactive desalted water by adopting S70.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311513387.6A CN117571387A (en) | 2023-11-14 | 2023-11-14 | Off-line sipping sampling device and sampling method for radioactive assembly |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202311513387.6A CN117571387A (en) | 2023-11-14 | 2023-11-14 | Off-line sipping sampling device and sampling method for radioactive assembly |
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| CN202311513387.6A Pending CN117571387A (en) | 2023-11-14 | 2023-11-14 | Off-line sipping sampling device and sampling method for radioactive assembly |
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| CN (1) | CN117571387A (en) |
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