CN117945496A - Method and device for removing residual tritium from filter core of waste filter in heavy water pile disposal pit - Google Patents
Method and device for removing residual tritium from filter core of waste filter in heavy water pile disposal pit Download PDFInfo
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- CN117945496A CN117945496A CN202311801878.0A CN202311801878A CN117945496A CN 117945496 A CN117945496 A CN 117945496A CN 202311801878 A CN202311801878 A CN 202311801878A CN 117945496 A CN117945496 A CN 117945496A
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- Prior art keywords
- tritium
- disposal pit
- molecular sieve
- filter element
- waste filter
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 title claims abstract description 119
- 229910052722 tritium Inorganic materials 0.000 title claims abstract description 119
- 239000002699 waste material Substances 0.000 title claims abstract description 98
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 title claims abstract description 66
- 238000000034 method Methods 0.000 title claims abstract description 26
- 239000002808 molecular sieve Substances 0.000 claims abstract description 71
- URGAHOPLAPQHLN-UHFFFAOYSA-N sodium aluminosilicate Chemical compound [Na+].[Al+3].[O-][Si]([O-])=O.[O-][Si]([O-])=O URGAHOPLAPQHLN-UHFFFAOYSA-N 0.000 claims abstract description 71
- 238000001179 sorption measurement Methods 0.000 claims abstract description 51
- 238000010438 heat treatment Methods 0.000 claims abstract description 20
- 238000007789 sealing Methods 0.000 claims abstract description 18
- 238000005303 weighing Methods 0.000 claims abstract description 9
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims description 30
- 238000001514 detection method Methods 0.000 claims description 17
- 229910052757 nitrogen Inorganic materials 0.000 claims description 13
- 239000007789 gas Substances 0.000 claims description 7
- 239000004568 cement Substances 0.000 claims description 4
- 229910001873 dinitrogen Inorganic materials 0.000 claims description 4
- 238000001914 filtration Methods 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 11
- 238000010586 diagram Methods 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000010865 sewage Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- 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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- Measurement Of Radiation (AREA)
Abstract
The invention relates to a method for removing tritium remained in a waste filter element in a heavy water pile disposal pit, which comprises the following steps: opening a top cover of a disposal pit of the waste filter element to be treated, weighing the waste filter element, and sealing and closing the disposal pit; determining the dosage of the molecular sieve, loading the molecular sieve into a tritium adsorption device and communicating with a disposal pit, and recording the weight of the molecular sieve in real time; detecting the tightness of the disposal pit and the molecular sieve; continuously heating the disposal pit to enable tritium-containing steam to pass through a molecular sieve in a tritium adsorption device; when the weight of the molecular sieve is recorded to be unchanged, tritium removal of the waste filter element is completed, the invention also comprises a device for removing tritium remained in the waste filter element in the heavy water pile disposal pit, and the tritium water content of the waste filter element can be greatly reduced after the tritium removal treatment is carried out on the waste filter element in the disposal pit by adopting the method and the device for removing the tritium remained in the waste filter element in the heavy water pile disposal pit in the temporary storage process without moving the waste filter element.
Description
Technical Field
The invention belongs to the technical field of treatment of waste filter elements in heavy water pile treatment pits, and particularly relates to a method and a device for removing tritium remained in a waste filter element in a heavy water pile treatment pit.
Background
Heavy water reactor nuclear power plants such as the class 2 700MWe CANDU-6 pressurized heavy water reactor introduced from canada. 7 systems of each unit are provided with water filters, the water filters are important equipment in the nuclear island radioactive water treatment system, and impurities such as suspended matters are filtered in a water using process of a primary loop of a reactor and related systems, so that the stable operation of the units and related systems is ensured; in the drainage process of a loop sewage disposal system, a waste liquid treatment system and the like, the radioactivity and the chemical component content of the waste liquid are reduced, and the waste liquid discharge is ensured to meet the local environmental protection policy.
The filter element needs to be replaced at regular intervals or when the pressure difference reaches a set value, and according to the specification of a power station, the waste filter element (hereinafter referred to as a waste filter element) needs to be loaded into a shielding container to be transported to a waste temporary storage warehouse for temporary storage when the contact dosage rate of the waste filter element is more than 2 mSv/h. The temporary storage mode is that the waste filter element is vertically placed in a temporary storage warehouse underground disposal pit, and the upper part of the disposal pit is covered with a top cover to realize the sealing temporary storage of the waste filter element.
Because the temporary stored waste filter element in the temporary storage warehouse has higher dosage rate and contains a large amount of tritium water, personnel cannot directly contact and treat the waste filter element in a close range, and any waste filter element treatment method needs to open a treatment pit top cover to remove the waste filter element from the treatment pit, so that the tritium water is likely to overflow and cause radiation hazard to the environment and personnel.
Disclosure of Invention
Aiming at the defects existing in the prior art, the invention aims to provide a method and a device for removing residual tritium of a waste filter element in a heavy water reactor disposal pit so as to realize the safe treatment of the waste filter element in the disposal pit.
In order to achieve the above purpose, the invention adopts the technical scheme that: a method for removing residual tritium from a waste filter element in a heavy water pile disposal pit comprises the following steps: opening a top cover of a disposal pit of the waste filter element to be treated, weighing the waste filter element, and sealing and closing the disposal pit; determining the dosage of the molecular sieve, loading the molecular sieve into a tritium adsorption device and communicating with a disposal pit, and recording the weight of the molecular sieve in real time; detecting the tightness of the disposal pit and the molecular sieve; continuously heating the disposal pit to enable tritium-containing steam to pass through a molecular sieve in a tritium adsorption device; and recording the weight of the molecular sieve until no change exists, and completing tritium removal of the waste filter element.
Further, the detection of the tightness of the disposal pit and the molecular sieve specifically comprises: firstly, filling nitrogen into the disposal pit, standing for a preset time, observing pressure change in the disposal pit to judge whether the disposal pit is sealed, and if the pressure in the disposal pit is kept constant, filling nitrogen into the tritium adsorption device, standing for the same preset time, and judging the tightness of the tritium adsorption device by observing whether the pressure in the tritium adsorption device is kept constant.
Further, the predetermined time is 2h.
Further, the nitrogen gas filled in the disposal pit is 0.2+/-0.02 kpa, and the banding charged in the tritium adsorption device is 0.1+/-0.02 kpa.
Further, when the treatment pit is continuously heated, the temperature in the treatment pit is controlled to be kept within a predetermined temperature range.
Further, the predetermined temperature is 120.+ -. 5 ℃.
Further, the recorded molecular sieve weight to unchanged is specifically: the molecular sieve in the tritium adsorption device is stably heated until the molecular sieve weight is unchanged within 45min, wherein the recording interval is 15min.
Further, after tritium removal of the waste filter element is completed, the method further comprises the steps of: the treated filter element is temporarily stored in a disposal pit or transported to a detection and transportation place at a designated place, and a molecular sieve in a tritium adsorption device is filled in a waste bucket for sealing temporary storage or cement fixing treatment.
The invention also provides a device for removing tritium remained in the filter element of the waste filter in the heavy water reactor disposal pit, which comprises the following components: the sealing module is used for opening a top cover of the disposal pit of the waste filter element to be treated, weighing the waste filter element, and sealing and closing the disposal pit; the dosage determining module is used for determining the dosage of the molecular sieve, loading the molecular sieve into a tritium adsorption device and communicating the molecular sieve with a disposal pit, and recording the weight of the molecular sieve in real time; the detection module is used for detecting the tightness of the disposal pit and the molecular sieve; the heating module is used for continuously heating the disposal pit to enable tritium-containing steam to pass through the molecular sieve in the tritium adsorption device; and the recording module is used for recording that tritium removal of the waste filter element is completed when the weight of the molecular sieve is unchanged.
Further, the device for removing tritium remained in the waste filter element in the heavy water reactor disposal pit further comprises an external gas bottle, and is used for filling nitrogen into the disposal pit and the tritium adsorption device; the heating module is arranged around the waste filter element in the disposal pit; and a filter is further arranged at the air outlet of the tritium removing device for removing residual tritium of the waste filter element in the heavy water pile disposal pit and is used for filtering discharged gas.
The invention has the following effects: on the basis of meeting the sealing temporary storage function of a treatment pit top cover on a waste filter element in a temporary storage warehouse of a current nuclear power plant, tritium removal treatment can be carried out on the waste filter element in the treatment pit in the temporary storage process without moving the waste filter element, the tritium water content of the waste filter element can be greatly reduced after the treatment, so that the treatment pit meets the related treatment or treatment requirements, the safe treatment of the waste filter element in the treatment pit is realized, the tritium water content in the waste filter element is obviously reduced, the contact dosage rate of the waste filter element is reduced, and a basis is provided for the subsequent treatment or treatment receiving of the waste filter element.
Drawings
FIG. 1 is a flow diagram illustration of a method of removing tritium from spent filter cartridge residue in a heavy water stack disposal pit;
FIG. 2 is a schematic diagram of a device for removing tritium from the filter core residue of a waste filter in a heavy water stack disposal pit;
FIG. 3 is a schematic flow diagram of the operation of a device for removing tritium from the spent filter cartridge in a heavy water stack disposal pit.
Detailed Description
The invention is further described below with reference to the drawings and detailed description.
As shown in FIG. 1, the invention provides a method for removing tritium remained in a waste filter element in a heavy water reactor disposal pit, which comprises the following steps:
S1, opening a top cover of a disposal pit of a waste filter element to be treated, weighing the waste filter element, and sealing and closing the disposal pit;
Specifically, open the useless filter core of waiting to handle and handle the hole top cap, long-range line hangs the operation and lifts up useless filter core and weigh, record weight M1 (initial weight M0), the useless filter core of returning to the position after weighing finishes, the line hangs with this device slowly put into the hole of handling perpendicularly in, replace former hole top cap of handling, sealed close is handled hole top cap.
S2, determining the dosage of the molecular sieve, loading the molecular sieve into a tritium adsorption device and communicating the molecular sieve with a disposal pit, and recording the weight of the molecular sieve in real time;
Specifically, the molecular sieve dosage before the movable tritium adsorption module operates is determined and loaded into the molecular sieve: molecular sieve amount v= { (M1-M0)/100 g } l; and loading 110-120% V molecular sieve into movable tritium adsorption device, calibrating automatic weight measuring sensor, closing the device, and connecting the device air outlet to high-efficiency filter.
S3, detecting tightness;
specifically, firstly, nitrogen is filled into the disposal pit, the disposal pit is kept stand for a preset time, the pressure change in the disposal pit is observed to judge whether the disposal pit is sealed, if the pressure in the disposal pit is kept constant, then the nitrogen is filled into the tritium adsorption device, the disposal pit is kept stand for the same preset time, and the tightness of the disposal pit is judged by observing whether the pressure in the tritium adsorption device is kept constant.
It can be appreciated that if the pressure of both the disposal pit and the tritium adsorption device remain constant, then the leak detection is qualified, completing the leak tightness test.
Further, the predetermined time is 2h.
Further, the nitrogen gas filled in the disposal pit is 0.2+/-0.02 kpa, and the nitrogen gas filled in the tritium adsorption device is 0.1+/-0.02 kpa.
S4, continuously heating the disposal pit, enabling tritium-containing steam to pass through a molecular sieve in the tritium adsorption device, and recording the weight of the molecular sieve;
Specifically, after the tightness detection is qualified, heating is started, the temperature in the disposal pit is controlled to be kept within a range of a preset temperature, the evaporated tritium-containing steam enters a tritium adsorption device, the tritium steam is adsorbed through a molecular sieve in the tritium adsorption device, and the heating is continuously and stably performed while the weight of the molecular sieve in the tritium adsorption device is measured and recorded.
Further, the predetermined temperature is 120.+ -. 5 ℃.
S5, recording that tritium removal of the waste filter element is completed when the weight of the molecular sieve is unchanged;
Specifically, when the molecular sieve in the tritium adsorption device is stably heated until the recorded value does not change significantly within 45min (the recording interval is 15 min), the heating is stopped after the tritium removal of the waste filter element is completed and nitrogen is slowly and continuously filled for 20min (repeated 3 times), and the tritium removal of the waste filter element is completed.
Further, after tritium removal of the waste filter element is completed, the method further comprises the steps of:
s6, temporarily storing the treated filter element in a disposal pit or conveying the filter element to a detection conveying place at a designated place, and loading the molecular sieve in the tritium adsorption device into a waste bin for sealing temporary storage or cement fixing treatment.
As shown in FIG. 2, the invention also provides a device for removing tritium remained in the filter core of the waste filter in the heavy water reactor disposal pit, which comprises the following components:
the sealing module is used for opening a top cover of the disposal pit of the waste filter element to be treated, weighing the waste filter element, and sealing and closing the disposal pit;
The dosage determining module is used for determining the dosage of the molecular sieve, loading the molecular sieve into a tritium adsorption device and communicating the molecular sieve with a disposal pit, and recording the weight of the molecular sieve in real time;
the detection module is used for detecting the tightness of the disposal pit and the molecular sieve;
the heating module is used for continuously heating the disposal pit, enabling the tritium-containing steam to pass through the molecular sieve in the tritium adsorption device, and recording the weight of the molecular sieve;
and the recording module is used for recording that tritium removal of the waste filter element is completed when the weight of the molecular sieve is unchanged.
Further, the device for removing residual tritium in the waste filter element in the heavy water reactor disposal pit further comprises an external gas cylinder, and the external gas cylinder is used for filling nitrogen into the disposal pit and the tritium adsorption device.
Further, the heating module is arranged around the waste filter element in the disposal pit.
Further, an efficient filter is further arranged at the air outlet of the tritium removing device for removing residual tritium of the filter element of the waste filter in the heavy water pile disposal pit and is used for filtering discharged gas.
Referring to fig. 2-3, taking a specific example as an illustration, the operation flow of the device is as follows:
Firstly, a waste filter element treatment pit top cover to be treated is opened, a remote crane is used for lifting the waste filter element to weigh, the weight M1 (initial weight M0) is recorded, the waste filter element is reset after the weighing is finished, the device is slowly and vertically placed in a treatment pit by a crane to replace the original treatment pit top cover, and the treatment pit top cover is sealed and closed. Determining the molecular sieve dosage and loading the molecular sieve before the movable tritium adsorption module operates: molecular sieve dosage
V= { (M1-M0)/100 g } l; and loading 110-120% V molecular sieve into movable tritium adsorption device, calibrating automatic weight measuring sensor, closing the device, and connecting the device air outlet to high-efficiency filter. Sealing and leakage detecting of the top cover and the tritium adsorption device before operation: and closing the valves 2 and 3, opening the valve 1, filling 0.2+/-0.02 kpa of nitrogen, closing the valve 1, standing for 2 hours, and judging the tightness of the top cover by observing the pressure value in the disposal pit. If the pressure is kept constant within 2 hours, the top cover leak detection is qualified. And slowly opening a No. 2 valve to enable nitrogen to enter the tritium adsorption device, closing the No. 2 valve after the pressure reaches 0.1+/-0.02 kpa, standing for 2 hours, and judging the tightness of the tritium adsorption device by observing the pressure value in the tritium adsorption device. If the pressure is kept constant within 2 hours, the tritium adsorption device is qualified in leak detection. And if the leak detection of the device top cover and the movable tritium adsorption device is qualified, the tightness detection of the operation device is finished, and the tightness of the device is qualified. After the leak detection of the device before operation is qualified, the valve No. 1 is closed, the valve No. 2 and the valve No. 3 are opened, heating is started, the temperature in a disposal pit is controlled to be kept within the range of 120+/-5 ℃, the evaporated tritium-containing steam is discharged through the air guide hole of the top cover, and the tritium steam is adsorbed by the molecular sieve in the device. The stable heating was continued while measuring and recording the molecular sieve weight in the tritium adsorption device. And (3) stably heating until the molecular sieve weight in the tritium adsorption device does not change significantly within 45min (the recording interval is 15 min), and considering that tritium removal of the waste filter element is completed, opening a valve No. 1, slowly and continuously filling nitrogen for 20min (repeating for 3 times), closing all the valves, stopping heating, and completing tritium removal of the waste filter element. The treated filter element can be temporarily stored in a disposal pit (the top cover of the original disposal pit is sealed) or transported to a detection and transportation position at a designated place, and the molecular sieve in the tritium adsorption device is filled into a waste bucket for sealing temporary storage or cement fixing treatment.
According to the embodiment, on the basis of meeting the sealing temporary storage function of the disposal pit top cover on the waste filter element in the temporary storage of the current nuclear power plant, tritium removal treatment can be carried out on the waste filter element in the disposal pit in the temporary storage process without moving the waste filter element, so that the tritium water content of the waste filter element can be greatly reduced after treatment, the treatment or disposal requirement is met, the safe treatment of the waste filter element in the disposal pit is realized, the tritium water content in the waste filter element is obviously reduced, the contact dosage rate of the waste filter element is reduced, and a foundation is provided for the subsequent treatment or disposal and reception of the waste filter element.
The embodiments of the present invention are not limited to the embodiments described in the specific embodiments, and those skilled in the art may obtain other embodiments according to the technical solutions of the present invention, which also belong to the technical innovation scope of the present invention.
Claims (10)
1. The method for removing the tritium remained in the filter core of the waste filter in the heavy water pile disposal pit is characterized by comprising the following steps:
opening a top cover of a disposal pit of the waste filter element to be treated, weighing the waste filter element, and sealing and closing the disposal pit;
Determining the dosage of the molecular sieve, loading the molecular sieve into a tritium adsorption device and communicating with a disposal pit, and recording the weight of the molecular sieve in real time;
Performing tightness detection;
continuously heating the disposal pit to enable tritium-containing steam to pass through a molecular sieve in a tritium adsorption device;
and recording the weight of the molecular sieve until no change exists, and completing tritium removal of the waste filter element.
2. The method for removing tritium remained in a waste filter cartridge in a heavy water pile disposal pit, as claimed in claim 1, wherein:
The detection of the tightness of the treatment pit and the molecular sieve is specifically as follows: firstly, filling nitrogen into the disposal pit, standing for a preset time, observing pressure change in the disposal pit to judge whether the disposal pit is sealed, and if the pressure in the disposal pit is kept constant, filling nitrogen into the tritium adsorption device, standing for the same preset time, and judging the tightness of the tritium adsorption device by observing whether the pressure in the tritium adsorption device is kept constant.
3. The method for removing tritium remained in the waste filter cartridge in the heavy water pile disposal pit as claimed in claim 2, wherein:
the predetermined time is 2 hours.
4. The method for removing tritium remained in the waste filter cartridge in the heavy water pile disposal pit as claimed in claim 2, wherein:
the nitrogen gas filled in the disposal pit is 0.2+/-0.02 kpa, and the band-up filled in the tritium adsorption device is 0.1+/-0.02 kpa.
5. The method for removing tritium remained in a waste filter cartridge in a heavy water pile disposal pit, as claimed in claim 1, wherein:
The temperature in the treatment pit is controlled to be kept within a predetermined temperature range while the treatment pit is continuously heated.
6. The method for removing tritium remained in the waste filter cartridge in the heavy water pile disposal pit as claimed in claim 5, wherein:
The predetermined temperature is 120 + -5 deg.c.
7. The method for removing tritium remained in a waste filter cartridge in a heavy water pile disposal pit, as claimed in claim 1, wherein:
The recorded molecular sieve weight to unchanged is specifically: the molecular sieve in the tritium adsorption device is stably heated until the molecular sieve weight is unchanged within 45min, wherein the recording interval is 15min.
8. The method for removing tritium remained in a waste filter cartridge in a heavy water pile disposal pit, as claimed in claim 1, wherein:
After tritium removal of the waste filter element is completed, the method further comprises the following steps:
The treated filter element is temporarily stored in a disposal pit or transported to a detection and transportation place at a designated place, and a molecular sieve in a tritium adsorption device is filled in a waste bucket for sealing temporary storage or cement fixing treatment.
9. The utility model provides a heavy water heap handles interior useless filter core residual tritium remove device of hole which characterized in that includes:
the sealing module is used for opening a top cover of the disposal pit of the waste filter element to be treated, weighing the waste filter element, and sealing and closing the disposal pit;
The dosage determining module is used for determining the dosage of the molecular sieve, loading the molecular sieve into a tritium adsorption device and communicating the molecular sieve with a disposal pit, and recording the weight of the molecular sieve in real time;
The detection module is used for detecting tightness;
the heating module is used for continuously heating the disposal pit to enable tritium-containing steam to pass through the molecular sieve in the tritium adsorption device;
and the recording module is used for recording that tritium removal of the waste filter element is completed when the weight of the molecular sieve is unchanged.
10. A heavy water pile disposal pit spent filter cartridge residual tritium removal apparatus as claimed in claim 9, wherein:
the device for removing the residual tritium in the waste filter element in the heavy water pile disposal pit further comprises an external gas cylinder, and is used for filling nitrogen into the disposal pit and the tritium adsorption device;
the heating module is arranged around the waste filter element in the disposal pit;
and an efficient filter is further arranged at the air outlet of the tritium removing device for removing residual tritium of the waste filter element in the heavy water pile disposal pit and is used for filtering discharged gas.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311801878.0A CN117945496A (en) | 2023-12-25 | 2023-12-25 | Method and device for removing residual tritium from filter core of waste filter in heavy water pile disposal pit |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311801878.0A CN117945496A (en) | 2023-12-25 | 2023-12-25 | Method and device for removing residual tritium from filter core of waste filter in heavy water pile disposal pit |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN117945496A true CN117945496A (en) | 2024-04-30 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311801878.0A Pending CN117945496A (en) | 2023-12-25 | 2023-12-25 | Method and device for removing residual tritium from filter core of waste filter in heavy water pile disposal pit |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117945496A (en) |
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2023
- 2023-12-25 CN CN202311801878.0A patent/CN117945496A/en active Pending
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