CN100495071C - Device for measuring radioactive contamination on inner surface of pipeline - Google Patents
Device for measuring radioactive contamination on inner surface of pipeline Download PDFInfo
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- CN100495071C CN100495071C CNB2007100486645A CN200710048664A CN100495071C CN 100495071 C CN100495071 C CN 100495071C CN B2007100486645 A CNB2007100486645 A CN B2007100486645A CN 200710048664 A CN200710048664 A CN 200710048664A CN 100495071 C CN100495071 C CN 100495071C
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- insulator
- pipeline
- stainless steel
- steel casing
- current collector
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- 238000011109 contamination Methods 0.000 title claims abstract description 44
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 41
- 238000005259 measurement Methods 0.000 claims abstract description 46
- 239000012212 insulator Substances 0.000 claims abstract description 37
- 229910001220 stainless steel Inorganic materials 0.000 claims abstract description 37
- 239000010935 stainless steel Substances 0.000 claims abstract description 37
- 238000004441 surface measurement Methods 0.000 claims description 12
- 238000000034 method Methods 0.000 abstract description 25
- 229920006395 saturated elastomer Polymers 0.000 abstract description 2
- 230000000694 effects Effects 0.000 description 11
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 8
- 239000000463 material Substances 0.000 description 7
- 239000011810 insulating material Substances 0.000 description 6
- 238000001514 detection method Methods 0.000 description 5
- 239000002245 particle Substances 0.000 description 5
- 238000003904 radioactive pollution Methods 0.000 description 5
- 239000000523 sample Substances 0.000 description 5
- 229910000831 Steel Inorganic materials 0.000 description 4
- 238000004140 cleaning Methods 0.000 description 4
- 238000005202 decontamination Methods 0.000 description 4
- 230000003588 decontaminative effect Effects 0.000 description 4
- 229910052742 iron Inorganic materials 0.000 description 4
- 238000007789 sealing Methods 0.000 description 4
- 239000010959 steel Substances 0.000 description 4
- 238000004458 analytical method Methods 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- 239000004411 aluminium Substances 0.000 description 2
- 229910052782 aluminium Inorganic materials 0.000 description 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 2
- 230000008030 elimination Effects 0.000 description 2
- 238000003379 elimination reaction Methods 0.000 description 2
- 238000005070 sampling Methods 0.000 description 2
- 230000007812 deficiency Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000003344 environmental pollutant Substances 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 231100000719 pollutant Toxicity 0.000 description 1
- 238000005514 radiochemical analysis Methods 0.000 description 1
- 230000009897 systematic effect Effects 0.000 description 1
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- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention discloses a device and a method for measuring radioactive contamination on the inner surface of a pipeline. The stainless steel shell is fixedly connected with the insulator, the current collector is arranged on a central axis of the insulator, and the reducing protection ring is in interference fit with the insulator. The measuring method of the invention is that the tube wall of the measured tube is used as the wall of the ionization chamber, the saturated working voltage is applied to the tube wall, the current collector in the measuring device for the radioactive contamination on the inner surface of the tube collects the ionized charges generated in the tube by the radioactive nuclide, the measurement of the radioactive activity is converted into the measurement of the saturation current of the tube, and the average contamination level of the inner surface of the tube is calculated according to the measured current data. The invention has the characteristics of high measuring speed and high accuracy. The average pollution level of the inner surface of the polluted pipeline can be conveniently and quickly measured.
Description
Technical field
The invention belongs to radioactive contamination material and the decontamination plant field thereof of handling, be specifically related to a kind of metallic conduit inside surface radioactive contamination measurement mechanism and measuring method, be particularly useful for measuring, can be the inner surface of pipeline level of pollution and whether reach cleaning and separate control and require to provide distinguishing rule through radioactive contamination in pipeline inner surface after the decontamination.
Background technology
In elimination of nuclear facilities process, at diameter less (＜150mm) measuring method of inside surface level of pollution mainly contains two kinds after the radioactive pollution pipeline decontamination: the direct method of measurement and the indirect method of measurement.
The direct method of measurement promptly uses common surface pollution measuring instrument that the radioactivity of its inside surface is directly measured.Directly measure and have following problem: the one, the probe of surface pollution measuring instrument can only place opening part and can not stretch into inside, and the 2nd, camber structure and plane probe measurement window can not coincide in the pipeline, and its makeover process is also very complicated.The 3rd, judge the whole level of pollution of an inner surface of pipeline, carry out multimetering after pipeline must being cut open.These reasons have caused measurement result can not reflect the activity and the surface contamination level of radioactive pollution pipeline inside surface truly.
Measuring indirectly is chemical wiping sampling analysis method.Wipe method is that inner surface of pipeline is carried out local wiping sampling, by chemical treatment and radiochemical analysis the residual quantity in the pipeline estimated.The indirect measurement method interior radiomaterial distribution of the fact-finding process of elimination of nuclear facilities source item at home pipeline at present is uneven.Wiping efficient in addition depends on the individual differences that is carried out wiping action by wipe surfaces degree of roughness, pollutant chemistry combination degree and wiping personnel.Therefore sample representation unfounded property not enough and wiping efficient has been brought very big error to analysis result.
Summary of the invention
The technical problem to be solved in the present invention provides a kind of radioactive contamination in pipeline inner surface measurement mechanism and measuring method, the ionization current that the charged particle that the radiomaterial of inner surface of pipeline is launched forms in air is measured, thereby reaches the purpose of radioactive contamination level in the measuring channel.
Radioactive contamination in pipeline inner surface measurement mechanism of the present invention comprises current collector, high-field electrode, tapered guard ring, insulator and stainless steel casing; Its annexation is, described stainless steel casing is the cylindrical shell of an end opening, and the top of stainless steel casing is provided with electric current collection pole socket and high-voltage power supply plug, and the openend of stainless steel casing is fixedlyed connected with spool insulator by screw; One space is arranged between insulator the inner and the stainless steel casing, and the insulator outer end radially is set with annular high-field electrode; Current collector is arranged on the central axis of insulator, and an end of current collector is fixedlyed connected with insulator by nut, and the other end is exposed to outside the insulator; Current collector is connected by current signal line with the current collector plug of stainless steel casing top center point setting; Tapered guard ring is arranged between stainless steel casing and the current collector, and tapered guard ring is stretched out insulator by ground wire and stainless steel casing ground connection, and insulator and tapered guard ring are interference fit.High-field electrode is connected with high-voltage plug by current signal line.
Stainless steel stainless steel casing, insulator and the tapered guard ring of measurement mechanism of the present invention are concentric circles.
Current collector plug in the radioactive contamination in pipeline inner surface measurement mechanism also is provided with the current signal line that is used for external weak current electrometer; The high-voltage power supply plug leads to high-tension cable, is used for external high voltage power supply.During measurement, tested pipeline is installed on the insulating support.
Diameter and length that measurement mechanism of the present invention is provided with current collector according to the diameter and the duct length of tested pipeline.
Principle of work of the present invention is to utilize the method for ionization chamber principle of work to measure the activity of the radiomaterial in the radioactive pollution pipeline, be about to the locular wall of pipeline as ionization chamber, it is applied saturated operating voltage, current collector by measurement mechanism of the present invention is collected the ionization electric charge that radioactive nuclide produces in pipeline, the mode of measuring radioactivity is converted to the method for measuring channel saturation current, calculate radioactivity in the pipeline by the current data that measures, the useful area according to radioactivity and pipeline calculates the average level of pollution of inner surface of pipeline again.
Radioactive contamination in pipeline inner surface measuring method of the present invention may further comprise the steps:
1. survey the measurement of factor η
At first will with tested pollution pipe material measure-alike, free of contamination pipeline is placed on the insulating support, with the end sealing of insulating material with pipeline, then a standard source is put into free of contamination pipeline, again the current collector in the surperficial radioactive contamination measurement mechanism is put into pipeline, then the high-tension cable in the described measurement mechanism is connected with weak current measurement of electrostatic meter with high-voltage power supply respectively with current signal line, open high-voltage power supply, read the measurement current value I by the weak current electrometer
1, by formula
Calculate theoretical current value I
2, detection efficiency
, and then according to formula
Calculate the numerical value of surveying factor η;
In the formula: E is at every turn the decay energy of charged particle of standard source nucleic, and e is an electron charge, and A is the activity of standard source, E
0Be mean ionization energy;
2. the measurement of pollution-free pipeline
Will with tested pollution pipe material measure-alike, free of contamination pipeline is placed on the insulating support, with the end sealing of insulating material with pipeline, high-tension cable in the measurement mechanism is connected with weak current measurement of electrostatic meter with high-voltage power supply respectively with current signal line, open high-voltage power supply, record background current value I by the weak current electrometer
bValue, average after the duplicate measurements for several times;
3. pollution duct survey
Replace pollution-free pipeline with the pollution pipeline, 2. measure, measure the current value I of polluting pipeline by the weak current electrometer by above-mentioned steps
aDuplicate measurements is averaged for several times.
4. pollute the calculating of the average soiling value W of inner surface of pipeline
According to formula
With
Calculate radioactive pollution pipeline inside surface total activity A and average soiling value W;
In the formula: the total activity of A-pollution inner surface of pipeline, Bq; I
aThe measurement electric current of-pollution pipeline (the approximate number of charged particles that is proportional to), A; I
b-be the background current of measurement mechanism, A; η-detection the factor, A/Bq; W-for polluting the average soiling value of inner surface of pipeline, Bq.cm
2Φ-for polluting pipe diameter, cm; L-for polluting the length of pipeline, cm.
Adopt radioactive contamination in pipeline inner surface measurement mechanism of the present invention and measuring method thereof, one-shot measurement can directly provide inner surface of pipeline total activity and average level of pollution.The accuracy height of measurement mechanism is compared with chemical wiping sample analysis with direct measurement, can avoid owing to the systematic error of popping one's head in the measured position can not coincide or the sample representation deficiency is brought.When the metal surface radioactive contamination is cleaning when separating the control level, the current ratio background current that its radioactive particle decay produces is high one more than the magnitude.
Whether inner surface of pipeline reaches the control level of separating that cleans after adopting the present invention can judge decontamination exactly.
Description of drawings
Fig. 1 is a radioactive contamination in pipeline inner surface measurement mechanism diagrammatic cross-section of the present invention
Fig. 2 is the working state schematic representation of radioactive contamination in pipeline inner surface measurement mechanism of the present invention
Among the figure: 1. high-field electrode 2. tapered guard ring 3. current collectors 4, insulator 5. nuts 7. high-voltage power supply plugs 8. current collector plug current signal lines (9,18,6) 10. ground wire 11. stainless steel casing gib screws (12,14) 15. pollute pipelines 16, insulating material 17. insulating supports 19. high-tension cables 20. high-voltage power supplies 21. weak current electrometers
Embodiment
Below in conjunction with accompanying drawing the specific embodiment of the present invention is described further
In Fig. 1～Fig. 2, radioactive contamination in pipeline inner surface measurement mechanism of the present invention comprises current collector 3, high-field electrode 1, tapered guard ring 2, insulator 4 and stainless steel casing 11; Its annexation is, described stainless steel casing 11 is the cylindrical shell of an end opening, and the top of stainless steel casing 11 is provided with electric current collection pole socket 8 and high-voltage power supply plug 7, and stainless steel casing 11 is fixedlyed connected with spool insulator 4 by gib screw 12; Between insulator 4 the inners and the stainless steel casing 11 space is arranged, insulator 4 outer ends radially are set with annular high-field electrode 1, and high-field electrode 1 is connected with insulator 4 by gib screw 14; Current collector 3 is arranged on the central axis of stainless steel casing 11 and insulator 4, and the center pit that an end of current collector 3 passes insulator 4 is fixedlyed connected with insulator 4 by nut 5, and the other end is exposed to outside the insulator 4; Current collector 3 is connected by electric signal 9 with the current collector plug 8 that stainless steel casing 11 top center points are provided with; Tapered guard ring 2 is arranged between stainless steel casing 11 and the current collector 3, and tapered guard ring 2 is stretched out insulator 4 by ground wire 10 and stainless steel casing 11 ground connection, and insulator 4 is an interference fit with tapered guard ring 2.High-field electrode 1 is fixing with insulator 4 usefulness gib screws 14, and passes insulator 4 with a long screw and pass through current signal line 6 and be connected with high-voltage power supply plug 7.
Described stainless steel casing 11 is the concentric circle with tapered guard ring 2.Insulator 4 in the present embodiment adopts polytetrafluoroethylmaterial material.
Current collector plug 8 in the radioactive contamination in pipeline inner surface measurement mechanism of the present invention also is connected with the current signal line 18 that is used for external weak current electrometer 21, and high-voltage power supply plug 7 leads to high-tension cable 19, is used for external high voltage power supply 20.
When measuring, tested pipeline is installed on the insulating support 17, the insulating material 16 of closed conduct is a polytetrafluoroethylmaterial material.
Radioactive contamination in pipeline inner surface measuring method of the present invention may further comprise the steps:
1. survey the measurement of factor η
At first will with tested pollution pipe material measure-alike, free of contamination pipeline is placed on the insulating support 17, with the end sealing of insulating material 16 with pipeline, then a standard source is put into free of contamination pipeline, again the current collector 3 in the surperficial radioactive contamination measurement mechanism is put into pipeline, then the high-tension cable in the described measurement mechanism 19 is connected with weak current measurement of electrostatic meter 21 with high-voltage power supply 20 respectively with current signal line 18, open high-voltage power supply 20, read the measurement current value I by weak current electrometer 21
1, by formula
Calculate theoretical current value I
2, detection efficiency
And then according to formula
Calculate the numerical value of surveying factor η;
In the formula: E is at every turn the decay energy of charged particle of standard source nucleic, and e is an electron charge, and A is the activity of standard source, E
0Be mean ionization energy;
2. the measurement of pollution-free pipeline
Will with tested pollution pipe material measure-alike, free of contamination pipeline is placed on the insulating support 17, with the end sealing of insulating material 16 with pipeline, high-tension cable in the measurement mechanism 19 is connected with weak current measurement of electrostatic meter 21 with high-voltage power supply 20 respectively with current signal line 18, open high-voltage power supply 20, record background current value I by weak current electrometer 21
bValue, average after the duplicate measurements for several times;
3. pollution duct survey
Replace pollution-free pipeline with polluting pipeline 15,2. measure, measure the current value I of polluting pipeline 15 by weak current electrometer 21 by above-mentioned steps
aDuplicate measurements is averaged for several times;
4. pollute the calculating of the average soiling value W of inner surface of pipeline
According to formula
With
Calculate radioactive pollution pipeline inside surface total activity A and average soiling value W;
In the formula: A is for polluting the total activity of inner surface of pipeline; I
aFor polluting the measurement electric current of pipeline; I
bBackground current for measurement mechanism; η is for surveying the factor; W is for polluting the average soiling value of inner surface of pipeline; Φ is for polluting pipe diameter; L is for polluting the length of pipeline.
Device of the present invention is applicable to that multiple radioactive nuclide is (as P
u239, A
m241, U235, U238 etc.) radioactive contamination level measure, below with P
u239 and A
m241 pollutions are carried out radioactive contamination level for example and are measured.
Embodiment 1 P
u239 pollute the pipeline radioactive contamination level measures
1. survey the measurement of factor η
Use standard P
uThe source, its activity A
sBe 1.33 * 10
5/ 2 π min, internal diameter of the pipeline are 146mm, and length is the pollution-free stainless steel pipes of 1m, measures I according to the mode of the step 1 in the above-mentioned radioactive contamination in pipeline inner surface measuring method
1Be 4.655 * 10
-11A is by formula
Calculate I
2Be 5.222 * 10
-11A brings the detection efficiency formula into
Draw η
1=89.1%, draw thus and survey factor η=1.32 * 10
-14A/Bq.
2. the measurement of pollution-free pipeline
According to the mode of the step 2 in the above-mentioned radioactive contamination in pipeline inner surface measuring method, the employing internal diameter is 146mm, and length is the pollution-free stainless steel pipes of 1m, and measuring background current Ib is 1.10 * 10
-13A.
3. pollution duct survey
According to the mode of the step 3 in the above-mentioned radioactive contamination in pipeline inner surface measuring method, the employing internal diameter is 146mm, and length is the pollution stainless steel pipes of 1m, duplicate measurements 18 times, the electric current I that records
aData as shown in table 1.
Table 1 (unit: pA)
| 1.867 | 1.872 | 1.989 | 1.976 | 1.898 | 1.885 | 2.039 | 2.207 | 2.064 |
| 1.870 | 2.007 | 2.005 | 1.994 | 1.989 | 2.043 | 2.097 | 2.009 | 2.090 |
Last table data are asked average to be got: I
a=1.994 * 10
-12A
4. pollute the calculating of the average soiling value W of inner surface of pipeline:
According to the mode of the step 4 in the above-mentioned radioactive contamination in pipeline inner surface measuring method, can calculate and pollute the average soiling value of pipeline and be: W=0.03Bqcm
-2
Separating the control level according to the iron and steel among the GB17567-1998 " cleaning that the iron and steel of nuclear facilities and aluminium recycle utilize is again separated the control level " is 0.08Bqcm
-2, this pollutes the average soiling value W=0.03Bqcm of pipeline
-2, being lower than national standard, can utilize again.Embodiment 2 A
m241 pollute the pipeline radioactive contamination level measures
1. survey the measurement of factor η
Use standard A
mThe source, its activity A
sBe 5.38 * 10
3/ 2 π min, internal diameter are 146mm, and length is the pollution-free stainless steel pipes of 1m, measures I according to the mode of the step 1 in the above-mentioned radioactive contamination in pipeline inner surface measuring method
1Be 1.931 * 10
-12A is by formula
Calculate I
2Be 2.247 * 10
-12A brings the detection efficiency formula into
Draw η
1=85.9%, draw thus and survey factor η=1.42 * 10
-11A/Bq.
2. the measurement of pollution-free pipeline
According to the mode of the step 2 in the above-mentioned radioactive contamination in pipeline inner surface measuring method, use internal diameter to be 146mm, length is the pollution-free stainless steel pipes of 1m, measures background current I
bBe 1.10 * 10
-13A.
3. pollution duct survey
According to the mode of the step 3 in the above-mentioned radioactive contamination in pipeline inner surface measuring method, use internal diameter to be 146mm, length is the pollution stainless steel pipes of 1m, duplicate measurements 18 times, the electric current I that records
aData as shown in table 2.
Table 2 (unit: pA)
| 1.036 | 1.027 | 0.975 | 1.030 | 0.930 | 1.147 | 1.156 | 1.000 | 1.031 |
| 0.996 | 1.033 | 1.051 | 0.932 | 0.998 | 0.936 | 0.938 | 1.029 | 1.010 |
Last table data are asked average to be got: I
a=1.014 * 10
-12A
4. pollute the calculating of the average soiling value W of inner surface of pipeline:
According to the mode of the step 4 in the above-mentioned radioactive contamination in pipeline inner surface measuring method, can calculate and pollute the average soiling value of pipeline and be: W=0.02Bqcm
-2
Separating the control level according to the iron and steel among the GB17567-1998 " cleaning that the iron and steel of nuclear facilities and aluminium recycle utilize is again separated the control level " is 0.08Bqcm
-2, this pollutes the average soiling value W=0.02Bqcm of pipeline
-2, being lower than national standard, can utilize again.
In the above-described embodiments, the voltage of high-voltage power supply is 400V.
Claims (3)
1. radioactive contamination in pipeline inner surface measurement mechanism, it is characterized in that: described measurement mechanism comprises current collector (3), high-field electrode (1), tapered guard ring (2), insulator (4) and stainless steel casing (11); Its annexation is, described stainless steel casing (11) is the cylindrical shell of an end opening, the top of stainless steel casing (11) is provided with electric current collection pole socket (8) and high-voltage power supply plug (7), and stainless steel casing (11) is fixedlyed connected with spool insulator (4) by gib screw; Between insulator (4) the inner and the stainless steel casing (11) space is arranged, insulator (4) outer end radially is set with annular high-field electrode (1); Current collector (3) is arranged on the central axis of insulator (4), and an end of current collector (3) is fixedlyed connected with insulator (4) by nut (5), and the other end is exposed to outside the insulator (4); Current collector (3) is connected by current signal line (9) with the current collector plug (8) that stainless steel casing (11) top center point is provided with; Tapered guard ring (2) is arranged between stainless steel casing (11) and the current collector (3), and tapered guard ring (2) is stretched out insulator (4) by ground wire (10) and stainless steel casing (11) ground connection; High-field electrode (1) is connected with high-voltage power supply plug (7) by current signal line (6); On current collector plug (8), also be provided with the current signal line (18) that is used for external weak current electrometer (21), on high-voltage power supply plug (7), also be provided with the high-tension cable (19) that is used for external high voltage power supply (20).
2. radioactive contamination in pipeline inner surface measurement mechanism according to claim 1 is characterized in that: described insulator (4) is an interference fit with tapered guard ring (2).
3. radioactive contamination in pipeline inner surface measurement mechanism according to claim 1 is characterized in that: described stainless steel casing (11) is a concentric circles with tapered guard ring (2).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2007100486645A CN100495071C (en) | 2007-03-17 | 2007-03-17 | Device for measuring radioactive contamination on inner surface of pipeline |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2007100486645A CN100495071C (en) | 2007-03-17 | 2007-03-17 | Device for measuring radioactive contamination on inner surface of pipeline |
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| CN101046514A CN101046514A (en) | 2007-10-03 |
| CN100495071C true CN100495071C (en) | 2009-06-03 |
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| CNB2007100486645A Expired - Fee Related CN100495071C (en) | 2007-03-17 | 2007-03-17 | Device for measuring radioactive contamination on inner surface of pipeline |
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Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101710149B (en) * | 2009-11-09 | 2012-06-20 | 中国电力科学研究院 | System for measuring current density of oil gas pipeline |
| CN103257356B (en) * | 2013-05-20 | 2015-12-02 | 中国工程物理研究院核物理与化学研究所 | Tritium concentration measurement mechanism in airtight container |
| JP6524758B2 (en) * | 2015-04-01 | 2019-06-05 | 富士電機株式会社 | Water monitor |
| CN109085633A (en) * | 2018-09-12 | 2018-12-25 | 中国工程物理研究院核物理与化学研究所 | A kind of high concentration tritium monitor and measurement method |
| CN110416058B (en) * | 2019-08-02 | 2022-10-18 | 陕西卫峰核电子有限公司 | Post-accident high-range area radiation monitoring ionization chamber insulation device and assembling method |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE794531A (en) * | 1972-02-01 | 1973-05-16 | Fiat Spa | DEVICE FOR DETECTION OF NEUTRONIC FLOW IN THE CORE OF A NUCLEAR REACTOR |
-
2007
- 2007-03-17 CN CNB2007100486645A patent/CN100495071C/en not_active Expired - Fee Related
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE794531A (en) * | 1972-02-01 | 1973-05-16 | Fiat Spa | DEVICE FOR DETECTION OF NEUTRONIC FLOW IN THE CORE OF A NUCLEAR REACTOR |
| DE2304451A1 (en) * | 1972-02-01 | 1973-08-09 | Fiat Spa | DEVICE FOR DETECTION OF THE NEUTRON FLOW IN A CORE OF A NUCLEAR REACTOR, IN PARTICULAR FOR SHIP PROPULSION SYSTEMS |
| FR2170109A1 (en) * | 1972-02-01 | 1973-09-14 | Fiat Spa | Neutron flux detector probe - for internal use in nuclear reactor core |
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