CN112146600A - Device and method for rapidly determining scab position in precipitation reactor - Google Patents
Device and method for rapidly determining scab position in precipitation reactor Download PDFInfo
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- CN112146600A CN112146600A CN202010842693.4A CN202010842693A CN112146600A CN 112146600 A CN112146600 A CN 112146600A CN 202010842693 A CN202010842693 A CN 202010842693A CN 112146600 A CN112146600 A CN 112146600A
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01B—MEASURING LENGTH, THICKNESS OR SIMILAR LINEAR DIMENSIONS; MEASURING ANGLES; MEASURING AREAS; MEASURING IRREGULARITIES OF SURFACES OR CONTOURS
- G01B15/00—Measuring arrangements characterised by the use of electromagnetic waves or particle radiation, e.g. by the use of microwaves, X-rays, gamma rays or electrons
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01B—MEASURING LENGTH, THICKNESS OR SIMILAR LINEAR DIMENSIONS; MEASURING ANGLES; MEASURING AREAS; MEASURING IRREGULARITIES OF SURFACES OR CONTOURS
- G01B15/00—Measuring arrangements characterised by the use of electromagnetic waves or particle radiation, e.g. by the use of microwaves, X-rays, gamma rays or electrons
- G01B15/02—Measuring arrangements characterised by the use of electromagnetic waves or particle radiation, e.g. by the use of microwaves, X-rays, gamma rays or electrons for measuring thickness
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
- G21F9/125—Processing by absorption; by adsorption; by ion-exchange by solvent extraction
Abstract
The invention belongs to the technical field of spent fuel post-treatment, and particularly relates to a device and a method for quickly determining a scab position in a precipitation reactor. The device for rapidly determining the scab position in the precipitation reactor is arranged on the precipitation reactor (1) and comprises a plurality of strip-shaped neutron detectors (2) arranged on the shell of the precipitation reactor (1) at intervals, a computer (5) connected with the lead-out signals of the neutron detectors (2) and a display device (6) connected with the computer (5). According to the invention, on the premise of not carrying out any disassembly operation on the precipitation reactor (1), whether scabbing occurs in the precipitation reactor (1) or not can be quickly judged and the scabbing position can be determined, so that the occurrence of critical safety accidents can be avoided, the safety of the spent fuel post-treatment process is improved, convenience is brought to the later cleaning work, and the normal operation of the spent fuel post-treatment process is ensured.
Description
Technical Field
The invention belongs to the technical field of spent fuel post-treatment, and particularly relates to a device and a method for quickly determining a scab position in a precipitation reactor.
Background
Spent fuel, also known as irradiated nuclear fuel, is spent nuclear fuel that has been subjected to irradiation, typically produced by a nuclear reactor in a nuclear power plant. From 3% to 4% of the uranium waste (spent fuel) that has been used, uranium and plutonium are chemically separated from the fission products, a technique known as spent fuel redissolution and reprocessing. The recovered uranium and plutonium can be recycled in the mixed oxide fuel of the nuclear power plant to produce more energy, thereby enabling the uranium resources to be more fully utilized and reducing the concentration requirements. Post-processing also aids in the final disposal of the waste by reducing the volume of the high level waste and removing plutonium.
Currently, the Prex (Purex) solvent extraction process is widely used in the nuclear fuel reprocessing industry. An important step in the process is plutonium oxalate precipitation process, and an important device used in the process is a precipitation reactor which is a cylindrical device with a conical bottom. The plutonium valorization, precipitation and cake aging are all carried out in this plant. The precipitation reactor may be mechanically or pneumatically agitated. However, in actual operation, the plutonium oxalate may scab on the inner wall of the precipitation reactor, and the scab is serious, which may cause a critical safety accident. There is therefore a need for a method of measuring whether or not there is scarring and the location of scarring within a precipitation reactor, and there is no method currently available that can simultaneously and accurately measure whether or not there is scarring within a precipitation reactor and determine the location of scarring.
Disclosure of Invention
The invention aims to provide a device and a method for simultaneously determining whether the precipitation reactor is scarred and the position of the scab, which can quickly measure whether the precipitation reactor is scarred and determine the position of the scab on the premise of not disassembling the precipitation reactor and is beneficial to an operator to remove the scab according to the position of the scab.
In order to achieve the purpose, the technical scheme adopted by the invention is that the device for quickly determining the scab position in the precipitation reactor is arranged on the precipitation reactor, and comprises a plurality of strip-shaped neutron detectors arranged on the outer shell of the precipitation reactor at intervals, a computer connected with the leading-out signals of the neutron detectors and a display device connected with the computer.
Further, the neutron detector is arranged in the neutron moderating body, and the material of the neutron moderating body is a high-density polyethylene material.
Further, the top end of the neutron detector is higher than the top end of the precipitation reactor, and the bottom end of the neutron detector is lower than the bottom end of the precipitation reactor.
Further, the neutron detector is internally provided with3He gas, the pressure is 4-10 atm.
Further, the number of the neutron detectors is at least 3.
Furthermore, the number of the lead-out signals of the neutron detector is two, and the two lead-out signals are respectively an upper-end lead-out signal and a lower-end lead-out signal.
Furthermore, the lead-out signal is connected to the computer through a data acquisition unit for analysis.
Further, the device also comprises an output module connected with the computer.
To achieve the above object, the present invention also discloses a method for rapidly determining a scab site in a precipitation reactor for the apparatus for rapidly determining a scab site in a precipitation reactor as described above, comprising the steps of:
step S1, determining the height of the scab spot inside the precipitation reactor according to the time difference between the upper end lead-out signal and the lower end lead-out signal led out by the neutron detector, to obtain a height coordinate, specifically: recording the time difference, counting the recorded time difference in different time ranges, making a relation graph of the time difference and the counting to obtain a peak value, arranging a radioactive source in the precipitation reactor, and utilizing the radioactive source to change the height of a scab point position for scaling to obtain a function of a height coordinate and the time difference;
step S2, determining the horizontal position of the scab point in the sedimentation reactor according to the difference of the neutron counting rates measured by the neutron detector to obtain a horizontal coordinate; the specific method comprises the following steps: a graph of the change of the neutron counting rate along with time is manufactured by utilizing a radioactive source, after the neutron counting rate measured by the neutron detector gradually tends to be stable, the radioactive source is moved in the horizontal direction, and a function of a horizontal coordinate and the neutron counting rate can be obtained according to the neutron counting rate measured by the neutron detector;
step S3, determining the position of the scar spot according to the height coordinate and the horizontal coordinate, which comprises the following steps: making a scar point position judgment graph, wherein the horizontal coordinate is the horizontal coordinate, the vertical coordinate is the height coordinate, the scar point position judgment graph is divided into a plurality of unit areas, and the number of scar points in different unit areas is counted, wherein the more the number is, the higher the scar probability is; the shape and the color of the scar spots in each unit area are changed along with the number of the scar spots in the unit area, and the position of the scar is judged according to the shape and the color of the scar spots; the relationship between the shape of the scar forming point and the scar forming probability is as follows: diamond > circle > square > star, the relation of the color of knot spots and knot probability is: red > yellow > green > blue.
The invention has the beneficial effects that:
according to the invention, on the premise of not carrying out any disassembly operation on the precipitation reactor, whether scabbing exists in the precipitation reactor or not can be rapidly judged and the scabbing position can be determined, so that the occurrence of critical safety accidents can be avoided, the safety of the spent fuel post-treatment process is improved, convenience is brought to the later-stage cleaning work, and the normal operation of the spent fuel post-treatment process is ensured.
Drawings
FIG. 1 is a schematic diagram of a plutonium oxalate precipitation process described in the background section;
FIG. 2 is a schematic view of the neutron detector disposed on a precipitation reactor in an embodiment of the invention;
FIG. 3 is a schematic diagram of the connections between the various components of an apparatus for rapidly determining the location of scarring within a precipitation reactor in accordance with embodiments of the present invention;
FIG. 4 is a graph of time difference versus count as described in the detailed description of the invention;
FIG. 5 is a graph of neutron count rate versus time, in accordance with an embodiment of the present invention;
FIG. 6 is a diagram illustrating a scar spot position determination according to an embodiment of the present invention;
in the figure: 1-a precipitation reactor, 2-a neutron detector, 3-a neutron moderator, 4-a data collector, 5-a computer, 6-a display device and 7-an output module.
Detailed Description
The invention is further described below with reference to the figures and examples.
The device for rapidly determining the scab position in the precipitation reactor is arranged on the precipitation reactor 1 and comprises a neutron detector 2, a neutron moderating body 3, a data acquisition unit 4, a computer 5 (an embedded working condition machine), a display device 6, an output module 7 and the like.
The top end of the neutron detector 2 is higher than the top end of the precipitation reactor 1, and the bottom end of the neutron detector 2 is lower than the bottom end of the precipitation reactor 1.
The neutron detector 2 is internally provided with3He gas, the pressure is 4-10 atm.
The two extraction signals of the neutron detector 2 are respectively an upper extraction signal and a lower extraction signal.
The invention also discloses a method for rapidly determining the scab position in the precipitation reactor, which is used for the device for rapidly determining the scab position in the precipitation reactor, and comprises the following steps:
step S1, determining the height of the scab spot inside the precipitation reactor 1 according to the time difference between the upper end lead-out signal and the lower end lead-out signal led out by the neutron detector 2, to obtain a height coordinate (y), specifically: recording the time difference, counting the counts of the time difference recorded in different time ranges, and making a relation graph of the time difference and the counts to obtain a peak value, as shown in fig. 4, wherein the heights of the scab point positions are different, and the time differences of the horizontal coordinates corresponding to the peak value are also different; arranging a radioactive source in the precipitation reactor 1, and utilizing the radioactive source to change the height of the scab point position for calibration to obtain a function of a height coordinate (cm) and a time difference (ns); "count" refers to the number of time differences acquired within a unit time range, for example, 1000 time differences are acquired, the selected time range is 1-100 seconds, 100 seconds are divided into 100 parts, two time differences are acquired within the time range of 1-2 seconds, respectively 1.2 seconds and 1.4 seconds, and then the count is 2; the time difference collected within the time range of 5-6 seconds is three, namely 5.2 seconds, 5.8 seconds and 5.5 seconds, the count is 3, and so on;
step S2, determining the horizontal position of the scab point in the sedimentation reactor 1 according to the difference of the neutron counting rates measured by the neutron detector 2 to obtain a horizontal coordinate (x); the specific method comprises the following steps: a graph showing the change of the neutron counting rate with time is manufactured by utilizing the radioactive source, as shown in fig. 5, after the neutron counting rate measured by the neutron detector 2 gradually tends to be stable, the radioactive source is moved in the horizontal direction, and a function of a horizontal coordinate (cm) and the neutron counting rate (cps) can be obtained according to the neutron counting rate measured by the neutron detector 2;
step S3, determining the position of the knot spot according to the height coordinate (y) and the horizontal coordinate (x), specifically: making a scar point position judgment graph, wherein the horizontal coordinate is a horizontal coordinate (x), the vertical coordinate is a height coordinate (y), the scar point position judgment graph is divided into a plurality of unit areas, and the number of scar points in different unit areas is counted, wherein the more the number is, the higher the scar probability is; the shape and the color of the scar spots in each unit area are changed along with the number of the scar spots in the unit area, and the position of the scar is judged according to the shape and the color of the scar spots; the relationship between the shape of the scar forming point and the scar forming probability is as follows: diamond > circle > square > star, the relation of the color of knot spots and knot probability is: red > yellow > green > blue.
For example, the whole coordinate area of the scar spot position determination map is 50cm in abscissa and 80cm in ordinate, which are divided according to 5cm × 5cm, and the whole coordinate area can be divided into 160 unit areas, and the number of scar spots in different unit areas is counted, wherein the more the number is, the higher the scar probability is, for example, when the number of scar spots exceeds 1000, the displayed scar spots are diamond-shaped and red in color; when the number of the knot spots exceeds 500, the displayed knot spots are circular and yellow; when the number of the knot spots exceeds 200, the displayed knot spots are square and green; when the number of the knot spots is less than 200, the displayed knot spots are star-shaped and blue in color. The probability of scarring is as follows: diamond > circle > square > star, red > yellow > green > blue, to determine the location of the nodal spots. Fig. 6 is an example of a scar spot position determination map, and it can be seen from the shape of the scar spots that the position of the scar spots in fig. 6 is approximately in the area of 15-19cm on the abscissa and 0-6cm on the ordinate, and diamond-shaped scar spots are densely displayed in the area.
The device according to the present invention is not limited to the embodiments described in the specific embodiments, and those skilled in the art can derive other embodiments according to the technical solutions of the present invention, and also belong to the technical innovation scope of the present invention.
Claims (9)
1. A device for rapidly determining the scab position in a precipitation reactor, which is arranged on the precipitation reactor (1), is characterized in that: the device comprises a plurality of strip-shaped neutron detectors (2) arranged on the shell of the precipitation reactor (1) at intervals, a computer (5) connected with the neutron detectors (2) and used for leading out signals, and a display device (6) connected with the computer (5).
2. The apparatus for rapidly determining the location of scarring in a precipitation reactor as recited in claim 1, wherein: the neutron detector (2) is arranged in the neutron moderating body (3), and the material of the neutron moderating body (3) is a high-density polyethylene material.
3. The apparatus for rapidly determining the location of scarring in a precipitation reactor as recited in claim 1, wherein: the top end of the neutron detector (2) is higher than the top end of the precipitation reactor (1), and the bottom end of the neutron detector (2) is lower than the bottom end of the precipitation reactor (1).
4. The apparatus for rapidly determining the location of scarring in a precipitation reactor as recited in claim 1, wherein: the neutron detector (2) is internally provided with3He gas, the pressure is 4-10 atm.
5. The apparatus for rapidly determining the location of scarring in a precipitation reactor as recited in claim 1, wherein: the number of the neutron detectors (2) is at least 3.
6. The apparatus for rapidly determining the location of scarring in a precipitation reactor as recited in claim 1, wherein: the two extraction signals of the neutron detector (2) are respectively an upper extraction signal and a lower extraction signal.
7. The apparatus for rapidly determining the location of scarring in a precipitation reactor as recited in claim 1, wherein: the lead-out signals are connected to the computer (5) through the data acquisition unit (4) for analysis.
8. The apparatus for rapidly determining the location of scarring in a precipitation reactor as recited in claim 1, wherein: and the device also comprises an output module (7) connected with the computer (5).
9. A method for rapid determination of the scab site in a precipitation reactor of an apparatus for rapid determination of the scab site in a precipitation reactor according to claim 1, comprising the steps of:
step S1, determining the height of a scar forming point inside the precipitation reactor (1) according to the time difference between the upper end lead-out signal and the lower end lead-out signal led out by the neutron detector (2), and obtaining a height coordinate, specifically: recording the time difference, counting the recorded time difference in different time ranges, making a relation graph of the time difference and the counting to obtain a peak value, arranging a radioactive source in the precipitation reactor (1), and utilizing the radioactive source to change the height of a scab point position for scaling to obtain a function of a height coordinate and the time difference;
step S2, determining the horizontal position of a knot scar inside the precipitation reactor (1) according to the difference of neutron counting rates measured by the neutron detector (2) to obtain a horizontal coordinate; the specific method comprises the following steps: a graph of the change of the neutron counting rate along with time is manufactured by utilizing a radioactive source, after the neutron counting rate measured by the neutron detector (2) gradually tends to be stable, the radioactive source is moved in the horizontal direction, and a function of a horizontal coordinate and the neutron counting rate can be obtained according to the neutron counting rate measured by the neutron detector (2);
step S3, determining the position of the scar spot according to the height coordinate and the horizontal coordinate, which comprises the following steps: making a scar point position judgment graph, wherein the horizontal coordinate is the horizontal coordinate, the vertical coordinate is the height coordinate, the scar point position judgment graph is divided into a plurality of unit areas, and the number of scar points in different unit areas is counted, wherein the more the number is, the higher the scar probability is; the shape and the color of the scar spots in each unit area are changed along with the number of the scar spots in the unit area, and the position of the scar is judged according to the shape and the color of the scar spots; the relationship between the shape of the scar forming point and the scar forming probability is as follows: diamond > circle > square > star, the relation of the color of knot spots and knot probability is: red > yellow > green > blue.
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Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1073013A (en) * | 1992-11-17 | 1993-06-09 | 水利部交通部能源部南京水利科学研究院 | Detect the method for concrete porosity under steel plate with neutron technology |
| KR20090067864A (en) * | 2007-12-21 | 2009-06-25 | 주식회사 포스코 | A technique for deposit detection in pipelines using gamma-ray |
| CN102109473A (en) * | 2009-12-29 | 2011-06-29 | 同方威视技术股份有限公司 | Method for imaging objects through photoneutron transmission and detector array |
| CN105132953A (en) * | 2015-07-24 | 2015-12-09 | 中国原子能科学研究院 | Spent fuel dry reprocessing method for directly obtaining zirconium alloy fuel |
| JP2017049028A (en) * | 2015-08-31 | 2017-03-09 | 国立研究開発法人日本原子力研究開発機構 | Debris deposition amount estimation device and estimation method |
| CN107561103A (en) * | 2017-09-08 | 2018-01-09 | 中国原子能科学研究院 | A kind of equipment for spent fuel storage rack boron Tube heating furnace |
| CN109271719A (en) * | 2018-09-27 | 2019-01-25 | 岭东核电有限公司 | A kind of method and system of lead bismuth heap radioactivity radiation of equipment shielding processing |
| CN110967728A (en) * | 2019-12-18 | 2020-04-07 | 成都理工大学 | Gridding area multi-mode neutron dose monitoring method |
-
2020
- 2020-08-20 CN CN202010842693.4A patent/CN112146600B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1073013A (en) * | 1992-11-17 | 1993-06-09 | 水利部交通部能源部南京水利科学研究院 | Detect the method for concrete porosity under steel plate with neutron technology |
| KR20090067864A (en) * | 2007-12-21 | 2009-06-25 | 주식회사 포스코 | A technique for deposit detection in pipelines using gamma-ray |
| CN102109473A (en) * | 2009-12-29 | 2011-06-29 | 同方威视技术股份有限公司 | Method for imaging objects through photoneutron transmission and detector array |
| CN105132953A (en) * | 2015-07-24 | 2015-12-09 | 中国原子能科学研究院 | Spent fuel dry reprocessing method for directly obtaining zirconium alloy fuel |
| JP2017049028A (en) * | 2015-08-31 | 2017-03-09 | 国立研究開発法人日本原子力研究開発機構 | Debris deposition amount estimation device and estimation method |
| CN107561103A (en) * | 2017-09-08 | 2018-01-09 | 中国原子能科学研究院 | A kind of equipment for spent fuel storage rack boron Tube heating furnace |
| CN109271719A (en) * | 2018-09-27 | 2019-01-25 | 岭东核电有限公司 | A kind of method and system of lead bismuth heap radioactivity radiation of equipment shielding processing |
| CN110967728A (en) * | 2019-12-18 | 2020-04-07 | 成都理工大学 | Gridding area multi-mode neutron dose monitoring method |
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（第三卷）——中国核学会2013年学术年会论文集第5册（辐射防护分卷、核化工分卷）》 * |
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