CN114895348A - Monitoring system for nuclear critical safety of precipitation reactor - Google Patents
Monitoring system for nuclear critical safety of precipitation reactor Download PDFInfo
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- CN114895348A CN114895348A CN202210549944.9A CN202210549944A CN114895348A CN 114895348 A CN114895348 A CN 114895348A CN 202210549944 A CN202210549944 A CN 202210549944A CN 114895348 A CN114895348 A CN 114895348A
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- 238000001556 precipitation Methods 0.000 title claims abstract description 123
- 238000012544 monitoring process Methods 0.000 title claims abstract description 44
- 239000013049 sediment Substances 0.000 claims abstract description 49
- 229910052778 Plutonium Inorganic materials 0.000 claims abstract description 13
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims abstract description 13
- ZQPKENGPMDNVKK-UHFFFAOYSA-N nitric acid;plutonium Chemical compound [Pu].O[N+]([O-])=O ZQPKENGPMDNVKK-UHFFFAOYSA-N 0.000 claims abstract description 11
- 239000002244 precipitate Substances 0.000 claims abstract description 9
- 238000005259 measurement Methods 0.000 claims description 33
- 238000009826 distribution Methods 0.000 claims description 29
- 230000005540 biological transmission Effects 0.000 claims description 22
- 238000007405 data analysis Methods 0.000 claims description 21
- 238000004140 cleaning Methods 0.000 claims description 6
- 238000003860 storage Methods 0.000 claims description 6
- 230000002452 interceptive effect Effects 0.000 claims description 4
- 238000004891 communication Methods 0.000 claims description 2
- 239000000203 mixture Substances 0.000 claims description 2
- 238000010521 absorption reaction Methods 0.000 claims 2
- 238000000034 method Methods 0.000 description 9
- MUBZPKHOEPUJKR-UHFFFAOYSA-N Oxalic acid Chemical compound OC(=O)C(O)=O MUBZPKHOEPUJKR-UHFFFAOYSA-N 0.000 description 6
- HRBJILZCKYHUJF-UHFFFAOYSA-J [Pu+4].[O-]C(=O)C([O-])=O.[O-]C(=O)C([O-])=O Chemical compound [Pu+4].[O-]C(=O)C([O-])=O.[O-]C(=O)C([O-])=O HRBJILZCKYHUJF-UHFFFAOYSA-J 0.000 description 6
- 230000002159 abnormal effect Effects 0.000 description 4
- 238000012360 testing method Methods 0.000 description 4
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 3
- 239000004698 Polyethylene Substances 0.000 description 3
- 229910052796 boron Inorganic materials 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- -1 polyethylene Polymers 0.000 description 3
- 229920000573 polyethylene Polymers 0.000 description 3
- KRHYYFGTRYWZRS-UHFFFAOYSA-N Fluorane Chemical compound F KRHYYFGTRYWZRS-UHFFFAOYSA-N 0.000 description 2
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 description 2
- 238000004364 calculation method Methods 0.000 description 2
- 239000000470 constituent Substances 0.000 description 2
- 230000003028 elevating effect Effects 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 235000006408 oxalic acid Nutrition 0.000 description 2
- 238000004088 simulation Methods 0.000 description 2
- 238000004458 analytical method Methods 0.000 description 1
- 238000001354 calcination Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000003365 glass fiber Substances 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- UTDLAEPMVCFGRJ-UHFFFAOYSA-N plutonium dihydrate Chemical compound O.O.[Pu] UTDLAEPMVCFGRJ-UHFFFAOYSA-N 0.000 description 1
- FLDALJIYKQCYHH-UHFFFAOYSA-N plutonium(IV) oxide Inorganic materials [O-2].[O-2].[Pu+4] FLDALJIYKQCYHH-UHFFFAOYSA-N 0.000 description 1
- 230000035755 proliferation Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/50—Reprocessing of irradiated fuel of irradiated fluid fuel, e.g. regeneration of fuels while the reactor is in operation
-
- 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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- Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
The embodiment of the invention discloses a monitoring system for nuclear critical safety of a precipitation reactor. Wherein the precipitation reactor is used for converting a plutonium nitrate solution into a plutonium precipitate, which deposits form adhering to the inner wall of the precipitation reactor. The monitoring system includes: the neutron measuring device is arranged outside the precipitation reactor and used for measuring the neutron counting rate of neutrons generated by the sediment; and the control device is connected with the neutron measuring device and used for acquiring the neutron counting rate, determining the thickness and/or the quality of the sediment according to the neutron counting rate and judging the nuclear critical safety state of the precipitation reactor.
Description
Technical Field
The embodiment of the invention relates to the technical field of nuclear critical safety, in particular to a monitoring system for nuclear critical safety of a precipitation reactor.
Background
In the plutonium tail end treatment of spent fuel reprocessing, the plutonium nitrate solution is mostly converted to solid plutonium dioxide by precipitation and calcination. There are various conversion methods, for example, using hydrogen peroxide, hydrofluoric acid, or oxalic acid to precipitate plutonium. Currently, plutonium precipitation processes are generally carried out using precipitation reactors. However, after the precipitation reactor is used for many times, the plutonium precipitates are easily accumulated and scabbed on the inner wall and the like, so that the mass of the plutonium in each batch of precipitation feed liquid is increased, and the nuclear critical safety risk is increased. In addition, as the sediment gradually accumulates, it may fall to the bottom of the settler to block the pipe, which may affect the normal operation of the precipitation reactor.
Disclosure of Invention
According to one aspect of the present invention, a monitoring system for precipitation reactor nuclear criticality safety is provided. Wherein the precipitation reactor is used for converting a plutonium nitrate solution into a plutonium precipitate, which adheres to form a deposit on the inner wall of the precipitation reactor. The monitoring system includes: the neutron measuring device is arranged outside the precipitation reactor and used for measuring the neutron counting rate of neutrons generated by the sediment; and the control device is connected with the neutron measuring device and used for acquiring the neutron counting rate, determining the thickness and/or the quality of the sediment according to the neutron counting rate and judging the nuclear critical safety state of the precipitation reactor.
Drawings
Other objects and advantages of the present invention will become apparent from the following description of the embodiments of the present invention with reference to the accompanying drawings, and may help to provide a full understanding of the present invention.
Fig. 1 is a schematic view of an application scenario of a monitoring system according to an embodiment of the present invention.
Fig. 2 is a cross-sectional view of the monitoring system of fig. 1.
Fig. 3 is a schematic structural diagram of a neutron measurement device according to an embodiment of the invention.
Fig. 4 is a cross-sectional view of the neutron measurement device of fig. 3.
Fig. 5 is a schematic structural view of a lifting device according to an embodiment of the present invention.
Fig. 6 is a schematic structural diagram of a monitoring system according to an embodiment of the present invention.
It is noted that the drawings are not necessarily to scale and are merely illustrative in nature and not intended to obscure the reader.
Description of reference numerals:
100. a neutron measurement device; 110. a neutron detector; 120. shielding the collimator; 121. a shield; 122. a moderator; 130. connecting a cable;
200. a control device; 210. a control module; 220. a data acquisition module; 230. a data analysis module; 240. a storage module; 250. an alarm module; 260. a display section; 270. an input section; 280. a power source;
300. a lifting device; 310. a support bar; 320. a first support plate; 321. a fixed part; 330. an axial moving part; 331. a drive member; 332. a transmission member; 340. a second support plate; 350. a fixing member;
10. a precipitation reactor; 11. (ii) a deposit; 12. and (7) an insulating layer.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more clear, the technical solutions of the present application will be described below in detail and completely with reference to the accompanying drawings of the embodiments of the present application. It should be apparent that the described embodiment is one embodiment of the present application and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the application without any inventive step, are within the scope of protection of the application.
It is to be noted that, unless otherwise defined, technical or scientific terms used herein shall have the ordinary meaning as understood by those of ordinary skill in the art to which this application belongs. If the description "first", "second", etc. is referred to throughout, the description of "first", "second", etc. is used only for distinguishing similar objects, and is not to be construed as indicating or implying a relative importance, order or number of technical features indicated, it being understood that the data described in "first", "second", etc. may be interchanged where appropriate. If "and/or" is presented throughout, it is meant to include three juxtapositions, exemplified by "A and/or B" and including either scheme A, or scheme B, or schemes in which both A and B are satisfied. Furthermore, spatially relative terms, such as "above," "below," "top," "bottom," and the like, may be used herein for ease of description to describe one element or feature's spatial relationship to another element or feature as illustrated in the figures, and should be understood to encompass different orientations in use or operation in addition to the orientation depicted in the figures.
One embodiment of the present invention provides a monitoring system for precipitation reactor nuclear criticality safety. Wherein the precipitation reactor 10 is used for converting a plutonium nitrate solution into a plutonium precipitate. As shown in fig. 2, the plutonium precipitate easily adheres to and deposits on the inner wall of the precipitation reactor 10 to form a deposit 11. In addition, the precipitation reactor 10 is provided with an insulating layer 12. The insulating layer 12, for example, insulating glass fiber, is wrapped on the outer wall of the precipitation reactor 10 to ensure the temperature condition required for the precipitation process.
In some examples, the plutonium nitrate solution is converted to a plutonium oxalate precipitate using oxalic acid. The deposit 11 in this embodiment may be plutonium oxalate precipitate. The plutonium oxalate precipitates fixed components, is well crystallized, is easy to filter and wash, has low plutonium oxalate solubility, and can obtain high plutonium recovery rate. In addition, the production process of plutonium oxalate is stable and easy to control, and continuous operation can be realized.
The monitoring system can be used for monitoring the nuclear critical safety of the precipitation reactor in the precipitation process of producing plutonium oxalate, thereby ensuring the nuclear critical safety and the industrial safety of the precipitation reactor in long-term use. Moreover, the neutron measurement device 100 is installed outside the precipitation reactor 10, so that the monitoring system does not affect the plutonium precipitation process during use.
As shown in fig. 1, the monitoring system in one embodiment of the present invention includes a neutron measurement device 100 and a control device 200. The neutron measurement device 100 is disposed outside the precipitation reactor 10. In some embodiments, the neutron measurement device 100 is disposed proximate to an exterior wall of the precipitation reactor 10. The neutron measurement device 100 is configured to measure a neutron count rate of neutrons generated by the sediment 11.
The control device 200 is connected to the neutron measurement device 100, and is configured to obtain the neutron count rate, determine the thickness and/or the mass of the sediment 11 according to the neutron count rate, and determine the nuclear critical safety state of the precipitation reactor. In some examples, the neutron measurement device 100 and the control device 200 are connected by a wire, for example, the neutron measurement device 100 is connected to the control device 200 by a connection cable 130, so as to realize communication between the neutron measurement device 100 and the control device 200.
The embodiment of the invention determines the thickness and/or the quality of the sediment 11 by detecting the neutron counting rate, and can judge whether the precipitation reactor 10 is normally and safely operated and judge the nuclear critical safety state of the precipitation reactor based on the thickness and/or the quality of the sediment 11, thereby ensuring the nuclear critical safety and the industrial safety of the precipitation reactor under long-term use.
Fig. 3 shows a schematic structural diagram of a neutron measurement device in an embodiment in accordance with the invention. Fig. 4 shows a cross-sectional view of the neutron measurement device of fig. 3.
As shown in fig. 2 to 4, the neutron measurement apparatus 100 includes a neutron detector 110 and a shield collimator 120. Wherein, the neutron detector 110 is used for measuring the neutron count rate, the shielding collimator 120 wrap up in the surface of the neutron detector 110 for the neutron that produces of interference neutron and collimation target deposit in the shielding environment, make the neutron detector 110 can only detect the neutron that the deposit 11 of the just right high position of neutron detector 110 produced, prevent that the neutron of other directions from incidenting to the neutron detector 110. In this embodiment, the deposit 11 at the height position directly facing the neutron detector 110 is the target deposit.
In particular, the shield collimator 120 includes a shield 121 and a moderator 122. The shield 121 is wrapped on the outer surface of the neutron detector 110, and the shield 121 is used for moderating and absorbing the interfering neutrons in the environment. Wherein, an incidence channel is arranged on one side of the shield 121 facing the precipitation reactor 10, and the incidence channel is used for providing a channel for neutrons generated by the sediment to be incident to the neutron detector 110. A moderator 122 is disposed in the incident channel for moderating fast neutrons generated by the sediment 11.
In one example, the shielding body 121 is boron-containing polyethylene, and the boron-containing polyethylene can effectively slow down the interfering neutrons in other directions into thermal neutrons and be absorbed by boron, so as to effectively shield the interfering neutrons in other directions. The other direction is a direction other than a direction in which the neutron detector 110 faces the precipitation reactor 10.
The moderating body 122 can effectively moderate fast neutrons generated by the sediment 11 into thermal neutrons, so that the number of the thermal neutrons obtained by the neutron detector 110 is maximized, and the detection efficiency of the neutron detector 110 is improved. In one example, the moderator 122 is polyethylene.
Optionally, the shielding collimator 120 is a cylinder, and the neutron detector 110 is disposed at a central position of the cylinder of the shielding collimator 120. The cylinder is provided with a moderator 122 facing the direction of the deposit 11.
In this embodiment, the moderator 122 is disposed in the direction in which the neutron detector 110 faces the sediment 11, and the shield 121 is covered in other directions, so that the neutron detector 110 can only detect neutrons generated by the sediment 11 at the height position in which the neutron detector 110 faces, and neutrons in other directions are prevented from being incident on the neutron detector 110 to cause interference, thereby performing a collimation effect.
In some embodiments, the shielding collimator 120 further comprises an absorbing layer. The shielding body 121 with be provided with the absorbed layer between the neutron detector 110, the absorbed layer is used for absorbing the warp the thermal neutron after the shielding body moderates to furthest absorb the interference neutron of other directions, improve shielding collimator 120 to the absorptivity of the interference neutron of other directions, further prevent the interference neutron of other directions from getting into neutron detector 110.
When the neutron measurement device 100 in this embodiment is located at a certain height position outside the precipitation reactor 10, only the neutron count rate at the height position can be detected, and thus the thickness and/or mass of the deposit at the height position can be obtained.
In order to detect the distribution of the sediments 11 throughout the precipitation reactor, the monitoring system in this embodiment may also comprise a lifting device 300. Neutron measuring device 100 install in on elevating gear 300, elevating gear 300 is used for the drive neutron measuring device 100 is in the axial direction of precipitation reactor 10 moves to measure the neutron count rate of the different height position of precipitation reactor 10 to realize the scanning measurement in the whole precipitation reactor axial direction.
The precipitation reactor 10 in this embodiment is an axisymmetric reactor, and the distribution of the deposits 11 is substantially the same in the circumferential direction of the inner wall at each height of the precipitation reactor 10. That is, at a certain height, the deposits 11 are evenly distributed on the inner wall in the circumferential direction of the precipitation reactor 10. Whereas the distribution of the deposits 11 varies considerably in the axial direction of the precipitation reactor 10. In one example, more of the sediment 11 is present in the bottom area of the inner wall of the precipitation reactor 10.
In this embodiment, the neutron measurement device 100 is driven by the lifting device 300 to move up and down in the axial direction of the precipitation reactor 10, so that the distribution of the sediments 11 in the axial direction of the precipitation reactor 10 can be determined. From said distribution in the axial direction, the respective conditions of the deposits 11 on the inner wall of the entire precipitation reactor 10 can be determined.
As shown in fig. 5, the lifting device 300 includes a support rod 310, a first support plate 320, and an axial moving part 330. Wherein, the lower end of the supporting rod 310 is provided with a fixing member 350, and the fixing member 350 can fix the supporting rod 310 on the ground. The first support plate 320 is slidably disposed along the support rod 310, and the neutron measurement device 100 is fixed to the first support plate 320. The axial moving part 330 is disposed on the first supporting plate 320, and is configured to drive the first supporting plate 320 to move along the supporting rod 310 in the axial direction, and the neutron measuring device 100 can be driven by the first supporting plate 320 moving up and down in the axial direction.
Specifically, the axial moving portion 330 includes a driving member 331 and a transmission member 332. The lifting device 300 further includes a second supporting plate 340, wherein the second supporting plate 340 is fixed on the supporting rod 310 and spaced from the first supporting plate 320. The transmission member 332 is rotatably connected between the first support plate 320 and the second support plate 340, and the first support plate 320 is provided with a transmission matching portion matching with the transmission member 332. The driving member 331 is mounted on the second support plate 340, an output shaft of the driving member 331 is connected to the transmission member 332, and the driving member 331 is configured to drive the transmission member 332 to rotate. The transmission member 332 rotates and can realize the movement of the first support plate 320 along the support rod 310 by the engagement of the transmission member and the transmission engagement portion.
In this embodiment, the driving member 331 is a driving motor, and the transmission member 332 is a lead screw.
In one example, a fixing portion 321 is disposed on the first support plate 320, and the fixing portion 321 is used for fixing the neutron measurement device 100. For example, the fixing portion 321 has a groove, and the neutron measuring device 100 can be positioned in the groove to prevent the neutron measuring device 100 from being displaced, and also prevent the neutron measuring device 100 from rotating to cause the moderator 122 to be displaced in a direction not facing the precipitation reactor 10.
Alternatively, the lifting device 300 may include a support rod, a first support plate, a second support plate, and an axial moving part. The first supporting plate and the second supporting plate are fixed on the supporting rod at intervals, the transmission piece of the axial moving part is rotatably connected between the first supporting plate and the second supporting plate, and the driving piece is installed on the first supporting plate or the second supporting plate and used for driving the transmission piece to rotate. The lifting device further comprises a fixing part for fixedly mounting the neutron measuring device. The fixing part is slidably arranged on the transmission part, a transmission matching part matched with the transmission part is arranged on the fixing part, and the fixing part can move up and down by rotating the transmission part.
As shown in fig. 6, the control device 200 of the monitoring system in this embodiment includes a control module 210, and the control module 210 is connected to the axial moving part 330, and is configured to control the neutron measurement device 100 to move to a specified height position in the axial direction of the precipitation reactor 10 at a fixed time, so as to implement scanning measurement of the neutron measurement device 100 at a fixed time and a fixed point in the axial direction. Illustratively, the control module 210 is configured to control the driving member 331, and thus control the neutron measuring device 100 to move from top to bottom in the axial direction of the precipitation reactor 10, and may move a predetermined distance at predetermined time intervals, so as to realize scanning measurement of the neutron measuring device 100 in the axial direction of the precipitation reactor 10, and thus obtain the thickness of the sediment 11 at each height position of the precipitation reactor 10.
In the present embodiment, the control device 200 includes a data acquisition module 220. The data acquisition module 220 is connected to the neutron measurement device 100 and is configured to acquire a count rate of neutrons detected by the neutron measurement device 100, so that the thickness and/or mass of the deposit 11 can be determined according to the detected count rate of neutrons.
The control device 200 further comprises a data analysis module 230 communicatively coupled to the data acquisition module 220. The data acquisition module 220 transmits the count rate of neutrons to the data analysis module 230, and the data analysis module 230 may receive the count rate of neutrons acquired by the data acquisition module 220, and thus analyze and process the detected count rate of neutrons to determine the thickness and/or mass of the deposit 11.
In one example, the linear relationship between the neutron count rate and the thickness of the deposit is calculated in advance based on a simulation. Based on the established model of the precipitation reactor with sediments of different thicknesses, the response and neutron count of the neutron detector under different thicknesses are calculated, and the relation between the neutron count rate and the thickness of the sediments is obtained as a linear relation.
The control device 200 in this embodiment further includes a storage module 240, and a linear relationship between the neutron counting rate and the thickness of the sediment 11 may be pre-stored in the storage module 240, so that the data analysis module 230 determines the thickness of the sediment 11 on the inner wall of the precipitation reactor 10, for example, the thickness of the sediment 11 at each height position in the axial direction of the precipitation reactor 10, according to the measured neutron counting rate and the linear relationship.
In the present embodiment, the correspondence relationship of the neutron count rate to the mass and distribution state of the deposit 11 can be determined based on the neutron count rate of the precipitation reactor 10 during the test run, the linear relationship, and the composition of the plutonium nitrate solution.
The monitoring system may be used to monitor the neutron count rate during commissioning of the precipitation reactor 10. During the test run of the precipitation reactor 10, the neutron counting rate is measured by the neutron measuring device 100, and the thickness of the sediment 11 is determined according to the measured neutron counting rate and the linear relation obtained by the pre-simulation calculation. After the determination of the thickness of the deposit 11, the quality of the deposit 11 is determined by combining the components of the plutonium nitrate solution normally processed in the precipitation reactor 10, including the plutonium nitrate solution constituents of the plutonium isotopes and the concentrations of the constituents or the proportions of the plutonium nitrate solution isotopes. And determining the corresponding relation between the neutron counting rate and the sediment 11 mass according to the calculated sediment 11 mass and the measured neutron counting rate.
In addition, after determining the thickness and mass of the sediments 11 at each height position in the axial direction of the precipitation reactor 10, the distribution state of the sediments 11 on the inner wall of the precipitation reactor 10 can be determined, and the distribution state comprises: the distribution of the deposits 11 in the axial direction of the precipitation reactor 10, for example, the distribution of the thickness and/or mass of the deposits 11 in the axial direction. And determining the corresponding relation between the neutron counting rate and the distribution state of the sediments 11 according to the distribution state of the sediments 11 obtained through calculation and analysis and the measured neutron counting rate.
Optionally, the corresponding relationship between the neutron counting rate and the mass and distribution state of the sediment 11 may be stored in the storage module 240, so that the monitoring system analyzes the detected neutron counting rate when the precipitation reactor 10 is in normal operation.
The data analysis module 230 in this embodiment may be configured to determine the mass and distribution of the sediments 11 on the inner wall of the precipitation reactor 10, for example, the thickness and/or mass distribution of the sediments 11 in the axial direction, according to the neutron count rates and the corresponding relationship between the neutron count rates and the mass and distribution of the sediments at different height positions of the precipitation reactor 10.
Before the precipitation reactor is put into operation, the precipitation reactor 10 can be scanned and measured by a neutron measurement device 100 in order to determine the mass and distribution of the sediments 11 on the inner wall of the precipitation reactor 10.
It should be noted that the height positions in the embodiment of the present invention represent the regions corresponding to different heights of the precipitation reactor 10. In one example, the precipitation reactor 10 may be divided into a plurality of layers from bottom to top, the height of each layer is a predetermined height value, and each height position represents an area corresponding to each layer of the precipitation reactor 10. For example, if the predetermined height value is 10cm, one of the height positions is a region corresponding to a height of 0 to 10cm of the precipitation reactor 10.
In some embodiments, the data analysis module is configured to indicate whether the precipitation reactor 10 needs cleaning based on the mass and distribution of the deposits 11 on the inner walls of the precipitation reactor 10.
Specifically, the data analysis module 230 may indicate that the precipitation reactor 10 needs to be cleaned when the mass or distribution of the sediments 11 is equal to or exceeds a set safety threshold, so as to give a clear use suggestion, timely remind a technician to clean the interior of the precipitation reactor before use, avoid danger, and improve the productivity of the equipment while ensuring nuclear critical safety.
For example, during a commissioning of the precipitation reactor 10, a technician may set a safety threshold based on the commissioning results (including neutron count rate and sediment thickness, mass, and distribution). The set safety threshold represents a range within which the precipitation reactor 10 is safe to operate. When the set safety threshold is equal to or exceeded, indicating a possible or imminent danger to the precipitation reactor 10, cleaning is required.
The control device 200 may include an input component 270, and a technician may input the set safety threshold in the control device 200 via the input component 270.
In addition, the data analysis module 230 may analyze and determine the current nuclear critical safety parameters of the precipitation reactor 10 according to the mass and distribution of the sediments 11 on the inner wall of the precipitation reactor 10. Optionally, the data analysis module 230 may calculate a current nuclear critical safety parameter of the precipitation reactor 10 according to the detected mass and distribution of the sediments 11 based on a pre-established precipitation reactor model. The nuclear-critical safety parameter comprises an effective proliferation factor.
In this embodiment, the normal operating range of the precipitation reactor 10 may be determined based on the neutron count rate of the precipitation reactor 10 during the test run.
Illustratively, the monitoring system may be used to monitor the neutron count rate during commissioning of the precipitation reactor 10. During the test operation of the precipitation reactor 10, the neutron counting rate is measured by the neutron measuring device 100, and the normal operation range of the neutron counting rate of the precipitation reactor 10 during normal operation is calculated based on a pre-established model. After the normal operating range is determined, the normal operating range may be stored in the storage module 240.
In this embodiment, the control device 200 further includes an alarm module 250. During the formal operation period of the precipitation reactor 10, the neutron measurement device 100 monitors the neutron counting rate of the precipitation reactor 10 in real time, and the data analysis module 230 is configured to determine whether the neutron counting rate monitored by the neutron measurement device 100 in real time is within a normal operation range. And when the neutron counting rate is within the normal operation range, the current state of the precipitation reactor 10 is normal operation, and the precipitation reactor is in a safe operation state. And when the neutron counting rate exceeds the normal operation range, indicating the alarm module 250 to give an alarm prompt, and indicating that the precipitation reactor 10 is in an abnormal state.
After receiving the alarm instruction of the data analysis module 230, the alarm module 250 may perform alarm prompting, for example, using sound, light, signal, etc. to alarm the addition of abnormal materials in the using process, thereby reducing the nuclear critical safety risk in the using process of the precipitation reactor and ensuring the safety of personnel and equipment.
In addition, the control device 200 in this embodiment further includes a display unit 260, and the display unit 260 is configured to display the detected neutron count rate and its variation curve along the axial direction, and the thickness, mass, and distribution of the deposit 11.
In one example, when the data analysis module 230 indicates that the precipitation reactor 10 requires cleaning, the display component 260 may also display the cleaning recommendation to instruct a technician to clean the precipitation reactor interior.
In one example, when the alarm module 250 alarms in a signal alarm mode, the display unit 260 is configured to display an alarm prompt. Optionally, the alarm prompt may be highlighted on the display part 260, so as to prompt a technician that the precipitation reactor is in an abnormal state in time.
The control device 200 further comprises a power supply 280, wherein the power supply 280 is at least used for supplying power to the control device 200 and the neutron measuring device 100. In one example, the power supply 280 can also provide power to the lifting device 300. In some embodiments, the monitoring system may be powered by an external power supply, e.g., the monitoring system may be plugged into the mains to draw power. The power supply 280 in this embodiment can be used as an emergency power supply, and after the monitoring system loses external power supply, the power supply 280 is used to supply power to the whole monitoring system, so that normal operation of the monitoring system is ensured, and a monitoring task can be normally completed.
The monitoring system in the embodiment of the invention can monitor the nuclear critical safety of the precipitation reactor, can clearly determine whether the interior of the precipitation reactor needs to be cleaned before use, can improve the equipment productivity while ensuring the nuclear critical safety, and can give clear guidance suggestions. The alarm device can give an alarm for an abnormal state in the using process, so that the nuclear critical safety risk is reduced, and the safety of personnel and equipment is ensured.
It should also be noted that, in the case of the embodiments of the present invention, features of the embodiments and examples may be combined with each other to obtain a new embodiment without conflict.
The above description is only an embodiment of the present invention, but the scope of the present invention is not limited thereto, and the scope of the present invention is subject to the scope of the claims.
Claims (16)
1. A monitoring system for the nuclear critical safety of a precipitation reactor, characterized in that said precipitation reactor is intended to convert a plutonium nitrate solution into a plutonium precipitate, which adheres to the inner wall of said precipitation reactor to form a deposit;
the monitoring system includes:
the neutron measuring device is arranged outside the precipitation reactor and used for measuring the neutron counting rate of neutrons generated by the sediment;
a control device connected with the neutron measurement device, the control device being configured to: and acquiring the neutron counting rate, determining the thickness and/or the quality of the sediment according to the neutron counting rate, and judging the nuclear critical safety state of the precipitation reactor.
2. The monitoring system of claim 1, wherein the neutron measurement device comprises:
a neutron detector for measuring a neutron count rate;
and the shielding collimator is wrapped on the outer surface of the neutron detector and is used for shielding interference neutrons in the environment and collimating neutrons generated by the target deposit.
3. The monitoring system of claim 2, wherein the shield collimator comprises:
a shield wrapped around an outer surface of the neutron detector, the shield being configured to slow and absorb interfering neutrons in an environment; an incidence channel is arranged on one side, facing the precipitation reactor, of the shielding body, and the incidence channel is used for providing a channel for neutrons generated by the sediment to be incident to the neutron detector;
and the moderating body is arranged in the incident channel and is used for moderating fast neutrons generated by the sediment.
4. The monitoring system of claim 3, wherein an absorption layer is disposed between the shield and the neutron detector, the absorption layer configured to absorb thermal neutrons moderated by the shield.
5. The monitoring system of claim 1, further comprising: the lifting device is used for driving the neutron measuring device to move in the axial direction of the precipitation reactor so as to measure the neutron counting rates of different height positions of the precipitation reactor.
6. The monitoring system of claim 5, wherein the lifting device comprises:
a supporting rod is arranged on the supporting rod,
the neutron measurement device comprises a first supporting plate, a second supporting plate and a neutron measurement device, wherein the first supporting plate is arranged along the supporting rod in a sliding manner;
the axial moving part is arranged on the first supporting plate and used for driving the first supporting plate to move along the supporting rod in the axial direction.
7. The monitoring system of claim 6, wherein the lifting device further comprises: the second supporting plate is fixed on the supporting rod;
the axial moving portion includes:
the transmission part is rotationally connected between the first supporting plate and the second supporting plate, and the first supporting plate is provided with a transmission matching part matched with the transmission part;
and the driving piece is arranged on the second supporting plate, is in driving connection with the transmission piece and is used for driving the transmission piece to rotate so as to drive the first supporting plate to move along the supporting rod.
8. The monitoring system according to claim 6 or 7, wherein the control device comprises:
and the control module is connected with the axial moving part and used for controlling the neutron measuring device to move to a specified height position in the axial direction of the precipitation reactor at regular time.
9. The monitoring system of claim 1, wherein the control device comprises:
and the data acquisition module is connected with the neutron measuring device and used for acquiring the neutron counting rate detected by the neutron measuring device.
10. The monitoring system of claim 9, wherein the control device further comprises:
the storage module is pre-stored with a linear relation between the neutron counting rate and the thickness of the sediment;
a data analysis module in communication with the data acquisition module, the data analysis module being configured to: and determining the thickness of the deposit on the inner wall of the precipitation reactor according to the measured neutron counting rate of the precipitation reactor and the linear relation between the neutron counting rate and the thickness.
11. The monitoring system of claim 10, wherein the data analysis module is further configured to:
and determining the quality and distribution of the sediment on the inner wall of the precipitation reactor according to the neutron counting rates of different height positions of the precipitation reactor and the corresponding relation between the neutron counting rates and the quality and distribution state of the sediment.
12. The monitoring system of claim 11 wherein the correspondence of the neutron count rate to the mass and distribution of the sediment is determined based on the neutron count rate of the precipitation reactor during a commissioning operation, the linear relationship, and the composition of the plutonium nitrate solution.
13. The monitoring system of claim 11, wherein the data analysis module is further configured to:
and analyzing and determining the current nuclear critical safety parameters of the precipitation reactor according to the mass and distribution of the sediments on the inner wall of the precipitation reactor.
14. The monitoring system of claim 11, wherein the data analysis module is to:
indicating whether the precipitation reactor needs cleaning according to the quality and distribution of the sediment on the inner wall of the precipitation reactor.
15. The monitoring system of claim 14, wherein the data analysis module is to:
indicating that the precipitation reactor needs cleaning when the mass or distribution of the deposits equals or exceeds a set safety threshold.
16. The monitoring system of claim 1, wherein the control device comprises: the data analysis module and the alarm module;
the data analysis module is configured to:
judging whether the neutron counting rate monitored by the neutron measuring device in real time is in a normal operation range;
and when the neutron counting rate exceeds the normal operation range, indicating the alarm module to give an alarm.
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| CN202210549944.9A CN114895348A (en) | 2022-05-20 | 2022-05-20 | Monitoring system for nuclear critical safety of precipitation reactor |
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| CN202210549944.9A CN114895348A (en) | 2022-05-20 | 2022-05-20 | Monitoring system for nuclear critical safety of precipitation reactor |
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Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2977822B1 (en) * | 1998-12-08 | 1999-11-15 | 核燃料サイクル開発機構 | In-situ plutonium measuring device |
| CN112146600A (en) * | 2020-08-20 | 2020-12-29 | 中国原子能科学研究院 | Device and method for rapidly determining scab position in precipitation reactor |
-
2022
- 2022-05-20 CN CN202210549944.9A patent/CN114895348A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2977822B1 (en) * | 1998-12-08 | 1999-11-15 | 核燃料サイクル開発機構 | In-situ plutonium measuring device |
| CN112146600A (en) * | 2020-08-20 | 2020-12-29 | 中国原子能科学研究院 | Device and method for rapidly determining scab position in precipitation reactor |
Non-Patent Citations (1)
| Title |
|---|
| 周成龙等: "后处理厂含钚物料的总中子测量方法研究", 中国核科学技术进展报告, vol. 3, 30 September 2013 (2013-09-30), pages 172 - 176 * |
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