CN109100772B - Online analysis monitoring method and device for spent fuel dissolving process - Google Patents
Online analysis monitoring method and device for spent fuel dissolving process Download PDFInfo
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Abstract
The invention belongs to the technical field of measurement of uranium plutonium content in waste cladding, and particularly relates to an online analysis monitoring method and device for a spent fuel dissolving process, wherein the method comprises the following steps: step S1, establishing a database of isotope composition information of the spent fuel assembly according to the first data; step S2, using the isotope composition information corresponding to the second data in the database as the measurement standard; step S3, obtaining a first measured value of the ray counting rate; step S4, obtaining a second measured value of the ray counting rate; step S5, obtaining a nuclide residual ratio through the first measurement value and the second measurement value; step S6, judging whether the nuclide residual ratio meets the standard of the dissolving and cleaning operation, if so, ending the dissolving and cleaning operation; if not, the dissolution cleaning operation is performed again on the waste cladding, and steps S3 to S5 are performed again.
Description
Technical Field
The invention belongs to the technical field of measurement of uranium plutonium content in waste cladding, and particularly relates to an online analysis monitoring method and device for a spent fuel dissolving process.
Background
Along with the rapid development of the nuclear industry in China, the accumulation of the spent fuel is increasing day by day. The spent fuel contains nuclear fuel such as unburnt U235, generated Pu239 and the like, and a plurality of fission products and transuranic elements. The spent fuel assembly is transported to a process line at the head end of a post-treatment plant after being cooled, is cut into a plurality of small sections by a shearing machine and then is loaded into an open hanging basket, and is dipped into solution such as nitric acid and the like to dissolve the core, so that the fuel is dissolved out of the shell; the waste cladding is the residue of the spent fuel assembly after shearing, acid leaching and cleaning; after the waste cladding is repeatedly leached and cleaned, the residual materials in the opening hanging basket are detected by a waste cladding measuring system, the residual materials in the waste cladding are controlled to be about 1 per mill of the initial quantity according to the requirements of the first-end process of the post-treatment plant, and the qualified waste cladding is discharged into a waste barrel to enter a post-treatment tail-end process line for treatment and disposal.
The measurement of foreign waste cladding is basically that after the dissolution is finished, an opening hanging basket with the waste cladding is placed into a specific measuring device for direct measurement, or the waste cladding is transferred into a waste barrel and then is transported into the measuring device for measurement, and after the measurement is finished, the waste cladding is directly transferred into waste storage. However, because the post-treatment process is not mature in China, the waste cladding may need to be continuously dissolved after being measured, and if the content of the residues cannot reach the index of 1 per thousand, the quantitative measurement of the waste cladding is very necessary to be directly carried out near the dissolving tank in order to reduce the transfer process.
Meanwhile, currently, the safety monitoring of the dissolving tank at home and abroad is usually to detect Kr85 gas overflowing in the dissolving process by installing equipment nearby the dissolving tank, judge the safety of the dissolving process by monitoring the stability of measured data, cannot directly give out important nuclides of interest, such as the real-time content of U/Pu, and belongs to indirect judgment.
Disclosure of Invention
In view of the above problems, the present invention is to design an online quantitative analysis monitoring device for spent fuel dissolution process, which can realize online in-situ quantitative measurement and analysis of spent cladding.
In order to achieve the above purposes, the technical scheme adopted by the invention is an online analysis monitoring method for a spent fuel dissolving process, which is used for online measurement of a measured spent fuel assembly and obtained waste cladding which are subjected to dissolving and cleaning operations, and comprises the following steps:
step S1, establishing a database of isotope composition information of the spent fuel assemblies according to first data, wherein the first data comprise types, burning depths, operation histories, initial enrichment degrees and cooling time of various spent fuel assemblies;
step S2, using isotope composition information corresponding to second data in the database as a measurement standard, wherein the measurement standard comprises a first nuclide content, and the second data refers to the burning depth and the cooling time of the spent fuel assembly to be measured;
step S3, obtaining a first measurement value of the ray count rate, wherein the first measurement value is a ray count rate value obtained by measuring the measured spent fuel assembly at the beginning stage of the dissolving and cleaning operation;
step S4, obtaining a second measured value of the ray counting rate, wherein the second measured value is a ray counting rate numerical value obtained by measuring the waste cladding after the dissolving and cleaning operation is finished;
step S5, obtaining a nuclide residual ratio through the first measurement value and the second measurement value;
step S6, judging whether the nuclide residual ratio meets the standard of the dissolving and cleaning operation, if so, ending the dissolving and cleaning operation; if not, the dissolving and cleaning operation is performed again on the waste cladding, and the steps S3 to S5 are performed again.
Further, step S2 includes setting a threshold value of the ray count rate, and during the dissolution cleaning operation, if the measured ray count rate exceeds the threshold value, it is determined that a system or an apparatus performing the dissolution cleaning operation is faulty, and an alarm is prompted.
Further, the ray counting rate is a neutron counting rate or a total gamma counting rate.
Further, the isotope composition information of the spent fuel assembly in the database is obtained in a simulation calculation mode, and the isotope composition information comprises U isotope composition information, Pu isotope composition information, key fission product content and transuranic element content.
In order to achieve the above purpose, the invention also discloses an online analysis monitoring device for the spent fuel dissolving process, which is used for the method, and the online analysis monitoring device comprises a measuring main body which is arranged around the periphery of the dissolving tank for dissolving and cleaning operation, and measuring equipment for detecting the measured spent fuel assembly and the ray counting rate of the waste cladding is arranged on the measuring main body.
Furthermore, the measuring equipment can be remotely controlled by an operator, so that remote data reading, parameter setting, opening and closing are realized.
Further, the measurement device is a neutron detector or a total gamma detector.
The invention has the beneficial effects that:
the method and the device provided by the invention can provide the change of the content of the concerned important nuclide in the dissolving tank along with the dissolving time and the dissolving frequency in real time, and are more accurate and reliable. The method and the device provided by the invention save the detection time of the waste cladding, reduce the operability of personnel, avoid the radiation typhoid of the operators, reduce the pollution of radioactive waste liquid to a certain extent, and have practical application significance
Drawings
Fig. 1 is a schematic diagram of an online analysis monitoring device for a spent fuel dissolution process according to an embodiment of the present invention;
in the figure: 1-measuring main body (provided with fission chamber detector), 2-hanging basket (placed with waste cladding), and 3-dissolving tank.
Detailed Description
The invention is further described below with reference to the figures and examples.
The invention provides an on-line analysis monitoring method for a spent fuel dissolving process, which is used for carrying out on-line measurement on a measured spent fuel assembly subjected to dissolving and cleaning operation and an obtained waste cladding and comprises the following steps:
step S1, establishing a database of isotope composition information of the spent fuel assemblies according to first data, wherein the first data comprise types, burning depths, operation histories, initial enrichment degrees and cooling time of various spent fuel assemblies; isotope composition information of the spent fuel assembly in the database is obtained in a simulation calculation mode, and the isotope composition information comprises U isotope composition information, Pu isotope composition information, key fission product content, transuranic element content and the like.
Step S2, according to the isotope composition information corresponding to the second data in the database as the measuring standard, the measuring standard includes the first nuclide content, the second data refers to the burning depth and the cooling time of the measured spent fuel assembly; setting a threshold value of the ray counting rate, and if the measured ray counting rate value exceeds the threshold value during the dissolution cleaning operation, determining that a system or equipment for performing the dissolution cleaning operation has a fault, and prompting and alarming; the ray counting rate is a neutron counting rate or a total gamma counting rate; the spent cladding is the residue of the spent fuel assembly after being sheared and cleaned, so the burning depth and the cooling time of the spent cladding are consistent with those of the corresponding spent fuel assembly, and the second data can be directly read from the label of the corresponding measured spent fuel assembly;
step S3, obtaining a first measured value of the ray count rate, wherein the first measured value is a ray count rate value obtained by measuring the spent fuel assembly to be measured at the beginning stage of the dissolving and cleaning operation;
step S4, obtaining a second measured value of the ray counting rate, wherein the second measured value is a ray counting rate numerical value obtained by measuring the waste cladding after the dissolving and cleaning operation is finished;
step S5, obtaining a nuclide residual ratio through a first measurement value and a second measurement value (the residual ratio is the ratio between the waste cladding and the material content in the initial measured spent fuel assembly), and obtaining a second nuclide content through multiplying the nuclide residual ratio by the first nuclide content in the measurement standard, wherein the second nuclide content is the nuclide content of the waste cladding;
step S6, judging whether the nuclide residual ratio meets the standard of the dissolving and cleaning operation, if so, ending the dissolving and cleaning operation; if not, the dissolution cleaning operation is performed again on the waste cladding, and steps S3 to S5 are performed again.
As shown in figure 1, the invention also discloses an online analysis monitoring device for the spent fuel dissolving process, which is used for the method, and the online analysis monitoring device comprises a measuring main body 1, wherein the measuring main body 1 is arranged around the periphery of a dissolving tank 3 for dissolving and cleaning operation, measuring equipment is arranged on the measuring main body 1, and the measuring equipment is used for detecting the ray counting rate of a measured spent fuel assembly and a waste cladding in the dissolving tank 3.
The measuring equipment can be remotely controlled by an operator, so that remote data reading, parameter setting, opening and closing are realized.
The measuring device is a neutron detector (such as a fission chamber detector) or a total gamma detector.
The on-line monitoring implementation operation flow of the device is as follows (taking an on-line analysis monitoring device which is provided with a fission chamber detector and used for the dissolution process of the spent fuel as an example):
1) calculating nuclide information in the waste cladding according to isotope composition information of the spent fuel assembly in the database; (the waste cladding is the residue obtained by shearing and cleaning the tested spent fuel assembly)
2) A hoisting device is adopted to place the waste cladding into the hanging basket 2, and the hanging basket 2 is placed into a fixed position in the dissolving tank 3;
3) setting measurement parameters according to measurement requirements;
4) starting fission chamber measurement after parameter setting is finished;
5) in the first cleaning process, a fission chamber is adopted to carry out integral measurement on the dissolving tank, and measurement data are recorded;
6) repeating the above process, and comparing the measured data with the first measured data, and recording as nuclide residual ratio;
7) if the nuclide residual ratio reaches the process cleaning standard, repeating the step 6) until the measured nuclide residual ratio reaches the process cleaning standard, and ending the measurement process.
And (4) combining the nuclide component information given in the step 5) and the nuclide residual ratio in the step 6) to calculate the residual amount in the waste cladding at the moment.
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 (7)
1. An on-line analysis monitoring method for a spent fuel dissolving process, which carries out on-line measurement on a measured spent fuel assembly and a waste cladding obtained during the dissolving and cleaning operation, comprises the following steps:
step S1, establishing a database of isotope composition information of the spent fuel assemblies according to first data, wherein the first data refers to types, burning depths, operation histories, initial enrichment degrees and cooling time of various spent fuel assemblies;
step S2, using isotope composition information corresponding to second data in the database as a measurement standard, wherein the measurement standard comprises a first nuclide content, and the second data refers to the burning depth and the cooling time of the spent fuel assembly to be measured;
step S3, obtaining a first measurement value of the ray count rate, wherein the first measurement value is a ray count rate value obtained by measuring the measured spent fuel assembly at the beginning stage of the dissolving and cleaning operation;
step S4, obtaining a second measured value of the ray counting rate, wherein the second measured value is a ray counting rate numerical value obtained by measuring the waste cladding after the dissolving and cleaning operation is finished;
step S5, obtaining a nuclide residual ratio through the first measurement value and the second measurement value;
step S6, judging whether the nuclide residual ratio meets the standard of the dissolving and cleaning operation, if so, ending the dissolving and cleaning operation; if not, the dissolving and cleaning operation is performed again on the waste cladding, and the steps S3 to S5 are performed again.
2. The method of claim 1, further comprising: step S2 further includes setting a threshold value of the ray count rate, and during the dissolution cleaning operation, if the measured ray count rate value exceeds the threshold value, it is determined that a system or an apparatus performing the dissolution cleaning operation is faulty, and an alarm is prompted.
3. The method of claim 2, further comprising: the ray counting rate is a neutron counting rate or a total gamma counting rate.
4. The method of claim 1, further comprising: the isotope composition information of the spent fuel assembly in the database is obtained in a simulation calculation mode and comprises U isotope composition information, Pu isotope composition information, key fission product content and transuranic element content.
5. An on-line analysis monitoring device for spent fuel dissolving process for realizing the method of any one of claims 1-4, which is characterized in that: the device comprises a measuring main body (1) which is arranged around a dissolving tank (3) for dissolving and cleaning operation, wherein the measuring main body (1) is provided with a measuring device for detecting a measured spent fuel assembly and the ray counting rate of the waste cladding.
6. The apparatus of claim 5, wherein: the measuring equipment can be remotely controlled by an operator, and remote data reading, parameter setting, opening and closing are realized.
7. The apparatus of claim 6, wherein: the measuring device is a neutron detector or an overall gamma detector.
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| CN112231897B (en) * | 2020-09-21 | 2024-03-22 | 中国原子能科学研究院 | Dissolver spent fuel shearing section modeling method for nuclear critical safety analysis |
| CN114188050B (en) * | 2021-12-01 | 2024-05-07 | 中国核电工程有限公司 | Passive monitoring method and system for undissolved fuel ratio of spent fuel dissolver |
| CN114152992B (en) * | 2021-12-01 | 2024-04-26 | 中国核电工程有限公司 | Passive monitoring method and system for blockage of feed hopper of spent fuel dissolver |
| CN117524335A (en) * | 2023-11-24 | 2024-02-06 | 上海交通大学 | Plutonium-238 efficient irradiation production method based on extremum burnup analysis method |
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