CN109100772A - A kind of on-line analysis monitoring method and device for spentnuclear fuel course of dissolution - Google Patents
A kind of on-line analysis monitoring method and device for spentnuclear fuel course of dissolution Download PDFInfo
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- CN109100772A CN109100772A CN201810895570.XA CN201810895570A CN109100772A CN 109100772 A CN109100772 A CN 109100772A CN 201810895570 A CN201810895570 A CN 201810895570A CN 109100772 A CN109100772 A CN 109100772A
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- dissolution
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- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/167—Measuring radioactive content of objects, e.g. contamination
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Abstract
The invention belongs to cladding waste uranium plutonium content measurement technical fields, more particularly to a kind of on-line analysis monitoring method and device for spentnuclear fuel course of dissolution, method includes the following steps: step S1, and the database of the isotopics information of irradiated fuel assembly is established according to the first data；Step S2, according to the second data in the database corresponding isotopics information as measurement standard；Step S3 obtains the first measured value of ray counting rate；Step S4 obtains the second measured value of ray counting rate；Step S5 obtains nucleic by the first measured value and the second measured value and remains ratio；Step S6, judges whether nucleic residual ratio meets the standard of dissolution cleaning operation, if it is, terminating dissolution cleaning operation；If it is not, then carrying out dissolution cleaning operation again to cladding waste, and step S3 to step S5 is executed again.
Description
Technical field
The invention belongs to cladding waste uranium plutonium content measurement technical fields, and in particular to a kind of for spentnuclear fuel course of dissolution
On-line analysis monitoring method and device.
Background technique
With the fast development of China's core cause, the accumulation of spentnuclear fuel is increasing.Containing burning incompletely in spentnuclear fuel
U235, generation nuclear fuels and some fission products and transuranic element such as Pu239.Irradiated fuel assembly transport after cooling to
Reprocessing plant head end processing line is cut into after several segments by cutter and is packed into opening hanging basket, immerses the lysates such as nitric acid
After carry out molten core, fuel is dissolved out from shell；Cladding waste is exactly the residual after clipped irradiated fuel assembly, acidleach and cleaning
Object；Cladding waste carries out the remaining material in opening hanging basket after leaching and cleaning repeatedly, through cladding waste measuring system
Detection, according to the requirement of reprocessing plant head end technique, the residue in cladding waste should be controlled 1 ‰ or so of initial number,
It is drained into pail for used dressings to enter in post-processing tail end processing line through the qualified cladding waste of detection and carries out processing disposition.
The measurement of external cladding waste is essentially all to be put into the opening hanging basket equipped with cladding waste specific after dissolution
Measuring device directly measured, or cladding waste is transferred in pail for used dressings, then be transported into measuring device measurement, measurement terminates
Afterwards, cladding waste is directly transferred to waste storage.And China is due to aftertreatment technology and prematurity, it may be necessary to be surveyed to cladding waste
After amount, if residuals content fails to reach 1 ‰ this index, need to be continued to dissolve, at this time in order to reduce transhipment process,
Directly carried out near dissolving tank cladding waste quantitative measurment work just very it is necessary to.
Carrying out security monitoring to dissolving tank both at home and abroad at present simultaneously is usually to pass through installation equipment detection dissolution in its vicinity
The Kr85 gas overflowed in the process judges the safety of course of dissolution by monitoring the consistent level of measurement data, can not
The concern nucleic for directly giving emphasis belongs to the judgement of indirect such as the real-time content of U/Pu.
Summary of the invention
In view of the above problems, the purpose of the present invention is design a kind of on-line quantitative analysis prison for spentnuclear fuel course of dissolution
Device is surveyed, which can be realized the measurement of online in situ quantitation and analysis of cladding waste.
To achieve the above objectives, the technical solution adopted by the present invention is that a kind of on-line analysis for spentnuclear fuel course of dissolution
Monitoring method carries out on-line measurement, packet in the tested irradiated fuel assembly and obtained cladding waste for carrying out dissolution cleaning operation
Include following steps:
Step S1 establishes the database of the isotopics information of irradiated fuel assembly, first number according to the first data
According to type, the burn-up level, history run, initial enrichment, cooling time for including the various irradiated fuel assemblies of finger；
Step S2, according to corresponding isotopics information is used as measurement mark in the database with the second data
Standard, the measurement standard include the first radionuclide content, second data refer to the tested irradiated fuel assembly burn-up level,
Cooling time；
Step S3 obtains the first measured value of ray counting rate, and first measured value, which refers to clean in the dissolution, to be grasped
The incipient stage of work measures the tested obtained ray counting rate numerical value of irradiated fuel assembly；
Step S4 obtains the second measured value of ray counting rate, and second measured value, which refers to clean in the dissolution, to be grasped
The obtained ray counting rate numerical value of the cladding waste is measured after work；
Step S5 obtains nucleic by first measured value and second measured value and remains ratio；
Step S6, judges whether the nucleic residual ratio meets the standard of the dissolution cleaning operation, if it is, knot
Shu Suoshu dissolves cleaning operation；If it is not, then carrying out the dissolution cleaning operation again to the cladding waste, and institute is executed again
Step S3 is stated to the step S5.
Further, further include the threshold values for setting ray counting rate in the step S2, the dissolution cleaning operation into
In row, if the ray counting rate numerical value measured is more than the threshold values, then it is assumed that the system for carrying out the dissolution cleaning operation
Or equipment breaks down, and prompts to alarm.
Further, the ray counting rate is neutron count rate or total Gama Count rate.
Further, the isotopics information of the irradiated fuel assembly in the database is in such a way that simulation calculates
Obtain, the isotopics information include U isotopics information, Pu isotopics information, crucial fission product content,
Transuranic element content.
To achieve the above objectives, it is molten for spentnuclear fuel that the invention also discloses a kind of one kind for the process described above
The on-line analysis monitoring device of solution preocess, the measurement including being circumferentially positioned at the dissolving tank periphery for the dissolution cleaning operation
Main body, the measurement main body are equipped with the measurement for detecting the ray counting rate of tested irradiated fuel assembly and the cladding waste
Equipment.
Further, the measuring device can remotely be controlled by operator, realize that long-range reading data, parameter are set
Fixed, open and close.
Further, the measuring device is neutron detector or total gamma detector.
The beneficial effects of the present invention are:
And through the invention provided by method and apparatus, then can provide the critical nuclide paid close attention in dissolving tank in real time
Content is with the variation of dissolution time, number, and more accurately and reliably, and the present apparatus uses relative measurement, does not need
Preparatory scale is carried out, measurement error is smaller.Method and apparatus provided by the present invention have saved the detection time to cladding waste, subtract
Lack personnel's operability, avoid the radiation typhoid fever of operator, and reduce the pollution of radioactive liquid waste to a certain extent,
Tool has significant practical applications
Detailed description of the invention
Fig. 1 is the on-line analysis monitoring device that spentnuclear fuel course of dissolution is used for described in the specific embodiment of the invention
Schematic diagram；
In figure: 1- measures main body (being equipped with fission chamber detector), and 2- hanging basket (is placed with cladding waste), 3- dissolving tank.
Specific embodiment
The invention will be further described with reference to the accompanying drawings and examples.
A kind of on-line analysis monitoring method for spentnuclear fuel course of dissolution provided by the invention, to carrying out dissolution cleaning
The tested irradiated fuel assembly and obtained cladding waste of operation carry out on-line measurement, include the following steps:
Step S1 establishes the database of the isotopics information of irradiated fuel assembly, the first data packet according to the first data
Include the type for referring to various irradiated fuel assemblies, burn-up level, history run, initial enrichment, cooling time；Weary combustion in database
Expect that the isotopics information of component obtains in such a way that simulation calculates, isotopics information includes U isotopics letter
Breath, Pu isotopics information, crucial fission product content, transuranic element content etc..
Step S2, according to corresponding isotopics information is surveyed as measurement standard in the database with the second data
Amount standard includes the first radionuclide content, and the second data refer to the burn-up level of tested irradiated fuel assembly, cooling time；Set ray
The threshold values of counting rate, in dissolution cleaning operation carries out, if the ray counting rate numerical value measured is more than threshold values, then it is assumed that into
The system or equipment of row dissolution cleaning operation breaks down, and prompts to alarm；Ray counting rate is neutron count rate or total gamma
Counting rate；Since cladding waste is exactly the residue after the clipped cleaning of irradiated fuel assembly, so the burn-up level of cladding waste, cooling
Time is consistent with the burn-up level of corresponding irradiated fuel assembly, cooling time, and the second data can be directly weary from being tested accordingly
It is read on the label of fuel assembly；
Step S3, obtains the first measured value of ray counting rate, and the first measured value refers to the beginning in dissolution cleaning operation
Phase measuring is tested the obtained ray counting rate numerical value of irradiated fuel assembly；
Step S4, obtains the second measured value of ray counting rate, and the second measured value refers to after dissolving cleaning operation
Measure the obtained ray counting rate numerical value of cladding waste；
Step S5, obtaining nucleic residual ratio by the first measured value and the second measured value, (residual ratio is exactly cladding waste
With the ratio in initial tested irradiated fuel assembly between material content), the in ratio and measurement standard is remained by nucleic
One radionuclide content is multiplied to obtain the second radionuclide content, and the second radionuclide content is the radionuclide content of cladding waste；
Step S6, judges whether nucleic residual ratio meets the standard of dissolution cleaning operation, if it is, it is clear to terminate dissolution
Wash operation；If it is not, then carrying out dissolution cleaning operation again to cladding waste, and step S3 to step S5 is executed again.
As shown in Figure 1, the invention also discloses a kind of online points for spentnuclear fuel course of dissolution for the above method
Monitoring device, including measurement main body 1 are analysed, measurement main body 1 is circumferentially positioned at 3 periphery of dissolving tank for dissolving cleaning operation, surveys
It measures main body 1 and is equipped with measuring device, measuring device is used to detect penetrating for the tested irradiated fuel assembly and cladding waste in dissolving tank 3
Line counting rate.
Measuring device can remotely be controlled by operator, realize long-range reading data, parameter setting, open and close.
Measuring device is neutron detector (such as fission chamber detector) or total gamma detector.
It is following (with dissolving for spentnuclear fuel equipped with fission chamber detector that the on-line monitoring of the device implements operating process
For the on-line analysis monitoring device of journey):
1) the nucleic information provided in cladding waste is calculated according to the isotopics information of the irradiated fuel assembly in database；
(cladding waste is exactly tested irradiated fuel assembly by the obtained residue of shearing cleaning)
2) cladding waste is put by hanging basket 2 using hanging apparatus, hanging basket 2 is put into the fixation position in dissolving tank 3；
3) according to measurement needs, measurement parameter is set；
4) after the completion of parameter setting, starting fission chamber measurement；
5) in first time cleaning process, whole measurement is carried out to dissolving tank using fission chamber, records measurement data；
6) it repeats the above process, and by the secondary measurement data compared with first time measurement data, is denoted as nucleic residual ratio；
7) if nucleic residual ratio is to reach technique to clean standard, repeats the above steps 6), obtained until measured
Nucleic residual ratio reach technique cleaning standard when, measurement process terminates.
The nuclide composition information gone out in conjunction with given in step 5) can be calculated with the nucleic residual ratio in step 6)
Residual quantity in cladding waste at this time.
Device of the present invention is not limited to embodiment described in specific embodiment, those skilled in the art according to
Technical solution of the present invention obtains other embodiments, also belongs to the scope of the technical innovation of the present invention.
Claims (7)
1. a kind of on-line analysis monitoring method for spentnuclear fuel course of dissolution, weary combustion is tested to carry out dissolution cleaning operation
Expect that component and obtained cladding waste carry out on-line measurement, includes the following steps:
Step S1 establishes the database of the isotopics information of irradiated fuel assembly, first data packet according to the first data
Include the type for referring to various irradiated fuel assemblies, burn-up level, history run, initial enrichment, cooling time；
Step S2, according to the second data in the database corresponding isotopics information as measurement standard, institute
Stating measurement standard includes the first radionuclide content, and second data refer to the burn-up level of the tested irradiated fuel assembly, cooling
Time；
Step S3, obtains the first measured value of ray counting rate, and first measured value refers in the dissolution cleaning operation
Incipient stage measures the tested obtained ray counting rate numerical value of irradiated fuel assembly；
Step S4, obtains the second measured value of ray counting rate, and second measured value refers in the dissolution cleaning operation knot
The obtained ray counting rate numerical value of the cladding waste is measured after beam；
Step S5 obtains nucleic by first measured value and second measured value and remains ratio；
Step S6, judges whether the nucleic residual ratio meets the standard of the dissolution cleaning operation, if it is, terminating institute
State dissolution cleaning operation；If it is not, then carrying out the dissolution cleaning operation again to the cladding waste, and the step is executed again
Rapid S3 to the step S5.
2. the method as described in claim 1, it is characterized in that: further including the valve for setting ray counting rate in the step S2
Value, in dissolution cleaning operation progress, if the ray counting rate numerical value measured is more than the threshold values, then it is assumed that carry out
The system or equipment of the dissolution cleaning operation breaks down, and prompts to alarm.
3. method according to claim 2, it is characterized in that: the ray counting rate is neutron count rate or total Gama Count
Rate.
4. the method as described in claim 1, it is characterized in that: the isotopics of the irradiated fuel assembly in the database
Information obtains in such a way that simulation calculates, and the isotopics information includes U isotopics information, Pu isotopics
Information, crucial fission product content, transuranic element content.
5. a kind of on-line analysis for spentnuclear fuel course of dissolution for realizing any one of claim 1-4 the method monitors
Device, it is characterized in that: include the measurement main body (1) for being circumferentially positioned at dissolving tank (3) periphery for the dissolution cleaning operation,
Measurement main body (1) is equipped with and sets for detecting the measurement of the ray counting rate of tested irradiated fuel assembly and the cladding waste
It is standby.
6. device as claimed in claim 5 is realized it is characterized in that: the measuring device can remotely be controlled by operator
Long-range reading data, parameter setting, open and close.
7. device as claimed in claim 6, it is characterized in that: the measuring device is neutron detector or total gamma detector.
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| CN201810895570.XA CN109100772B (en) | 2018-08-08 | 2018-08-08 | Online analysis monitoring method and device for spent fuel dissolving process |
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| CN201810895570.XA CN109100772B (en) | 2018-08-08 | 2018-08-08 | Online analysis monitoring method and device for spent fuel dissolving process |
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| CN109100772A true CN109100772A (en) | 2018-12-28 |
| CN109100772B CN109100772B (en) | 2020-06-30 |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112231897A (en) * | 2020-09-21 | 2021-01-15 | 中国原子能科学研究院 | Dissolver spent fuel shear section modeling method for nuclear critical safety analysis |
| CN114152992A (en) * | 2021-12-01 | 2022-03-08 | 中国核电工程有限公司 | Passive monitoring method and system for blockage of feed hopper of spent fuel dissolver |
| CN114188050A (en) * | 2021-12-01 | 2022-03-15 | 中国核电工程有限公司 | Passive monitoring method and system for undissolved fuel ratio of spent fuel dissolver |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112231897A (en) * | 2020-09-21 | 2021-01-15 | 中国原子能科学研究院 | Dissolver spent fuel shear section modeling method for nuclear critical safety analysis |
| 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 |
| CN114152992A (en) * | 2021-12-01 | 2022-03-08 | 中国核电工程有限公司 | Passive monitoring method and system for blockage of feed hopper of spent fuel dissolver |
| CN114188050A (en) * | 2021-12-01 | 2022-03-15 | 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 |
| 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 |
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