CN110308477B - Method for calibrating tritium measuring ionization chamber by using gamma solid source - Google Patents

Method for calibrating tritium measuring ionization chamber by using gamma solid source Download PDF

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CN110308477B
CN110308477B CN201910462380.3A CN201910462380A CN110308477B CN 110308477 B CN110308477 B CN 110308477B CN 201910462380 A CN201910462380 A CN 201910462380A CN 110308477 B CN110308477 B CN 110308477B
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tritium
ionization chamber
solid source
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杨冬
董建峰
夏善杰
苏国权
何理
贺常娥
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CNNC Nuclear Power Operation Management Co Ltd
Third Qinshan Nuclear Power Co Ltd
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    • G—PHYSICS
    • 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
    • G—PHYSICS
    • 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
    • G01T1/185—Measuring radiation intensity with ionisation chamber arrangements
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T7/00—Details of radiation-measuring instruments
    • G01T7/005—Details of radiation-measuring instruments calibration techniques
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/10—Nuclear fusion reactors

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Abstract

The invention belongs to the technical field of radioactivity measurement and application, and provides a method for calibrating a tritium measuring ionization chamber by using a gamma solid source, aiming at the problems of high purchase cost and complex process caused by the fact that a tritium gas source is required in the conventional tritium measuring ionization chamber calibration method. The technical scheme of the invention is verified by two calibration periods, and the calibration work of the tritium measuring ionization chamber can be equivalently completed. The response deviation of the tritium measuring ionization chamber calibrated by adopting the gamma solid source to the field tritium level can meet the standard response deviation requirement, the calibration result meets the expectation, the calibration result of the new technology is marked to be normal, and the technology can realize the calibration of the tritium measuring ionization chamber of the CANDU unit by replacing a tritium gas source.

Description

Method for calibrating tritium measuring ionization chamber by using gamma solid source
Technical Field
The invention belongs to the technical field of radioactivity measurement and application, and particularly relates to a method for calibrating a tritium measurement ionization chamber by using a gamma solid source.
Background
Compared with radioactive products of a pressurized water reactor unit, the CANDU unit has a special radioactive product tritium, and is a professional key monitoring object for radiation protection of the CANDU unit. At present, tritium monitoring system in the air has been laid out and has been accomplished, and sampling point evenly distributed is in nuclear island and auxiliary factory building region, and the tritium level of area, key equipment and the high risk area of revealing of system effective monitoring key area, wherein, two units total 25 survey tritium rack (every rack contains 2 measurement ionization chambers and 2 compensation ionization chambers), and at present, tritium monitoring on-line system equipment all adopts the ionization chamber to survey the tritium principle in the air of unit. According to national standards, dosage equipment needs to be calibrated regularly, the completeness of the function of radiation measurement equipment and the accuracy of real-time measurement data are ensured, and the safety performance of a unit is improved. According to the industrial specification, for the calibration work of tritium measurement ionization chambers (each ionization chamber has low, medium and high ranges), the standard working scheme is that a tritium gas source with standard activity (theoretically, tritium gas sources with three different activity levels are needed in each range) is led into a chamber of the ionization chamber, and after full response is carried out through the ionization chamber, an output value is adjusted (in a theoretical state, the output value is the same as the theoretical value), so that the calibration work is completed.
Then, the scheme of calibrating and measuring the tritium ionization chamber by using a tritium gas source needs to invest a large production cost and management cost; taking field experience as an example, the procurement of the tritium gas source must obtain the permission of relevant departments at the national, province, city, county and company level, finally provides a procurement application after the approval is obtained, and a party B provides a sale application in Canada, and produces a standard product after the approval and the authorization of the Canada authority, and delivers the standard product on time according to a contract plan. After the tritium gas bottle source arrives at home, the tritium gas bottle source arrives at a company through multiple steps of acceptance, clearance and transportation, and enters the company through a radioactive source management flow inside the company and is posted by a radioactive source manager. But after single calibration, the tritium gas source in the bottle is exhausted, and radioactive source management personnel carry out a radioactive source scrapping process. In view of the fact that a lot of cost is generated in the purchase process of the tritium source, a new tritium measuring ionization chamber calibration method needs to be provided to equivalently complete the calibration work of the tritium measuring ionization chamber.
Disclosure of Invention
The invention aims to solve the problems of high purchase cost and complex process caused by the fact that a tritium gas source is needed to be used in the existing tritium measuring ionization chamber calibration method, and provides a method for calibrating a tritium measuring ionization chamber by using a gamma solid source, wherein a Cs-137 source is used for replacing the tritium gas source to calibrate the tritium measuring ionization chamber, so that the calibration work of the tritium measuring ionization chamber can be equivalently completed.
The invention provides a method for calibrating a tritium measuring ionization chamber by using a gamma solid source, which is characterized in that the gamma solid source is used for replacing a standard tritium gas source to calibrate the tritium measuring ionization chamber.
On the basis, the invention also provides a method for calibrating the tritium measuring ionization chamber by using the gamma solid source, which sequentially comprises the following steps:
step 1, using a gamma solid source to respond to a tritium measurement ionization chamber, and finding out a position where the tritium measurement ionization chamber responds to the gamma solid source with the maximum data to serve as a calibration position;
step 2, recording the maximum response data of the functional tritium measuring ionization chamber to the gamma solid source as an original parameter;
step 3, calculating the radioactivity of the gamma solid source working day before calibration work, and calculating theoretical response data B of the tritium measurement ionization chamber to the gamma solid source under the current activity according to the original parameters and the radioactivity of the gamma solid source working day by utilizing the linear rule of the tritium measurement ionization chamber to the gamma solid source response curve;
step 4, starting to calibrate the tritium-measuring ionization chamber, fixing the gamma solid source at the calibration position determined in the step 1, and recording the real response data C of the tritium-measuring ionization chamber to the gamma radioactive source after the response data of the tritium-measuring ionization chamber to be measured are stable;
step 5, calculating response deviation eta according to the theoretical response data obtained by the calculation in the step 3 and the real response data obtained by the step 4, wherein the eta = (C-B)/B is 100%;
step 6, when the absolute value of the response deviation eta is not greater than the standard response deviation eta', judging that the calibration data of the ionization chamber meets the expectation, thereby completing the calibration work; when the absolute value of the response deviation η is larger than the standard response deviation η ', the output value C' of the tritium measurement ionization chamber is adjusted to be consistent with the theoretical response data B, or the output value C '= (1 ± η') B of the tritium measurement ionization chamber is adjusted.
Further, in the step 2, two or more gamma solid sources are adopted to respectively measure the maximum response data of the tritium ionization chamber to the gamma solid sources, the radioactivity of the gamma solid sources is taken as the abscissa, the maximum response data of the tritium ionization chamber to the gamma solid sources is taken as the ordinate, and the slope of the curve is calculated by adopting multi-point fitting to serve as the original parameters.
Further, the standard response deviation η' is determined as follows:
Figure GDA0003895806500000031
description of the drawings: the standard response deviation is based on big data of historical response deviation of all archived radiation monitoring equipment since the heavy water reactor unit operates, deviation trends of different types of instruments are comprehensively considered, meanwhile, uncontrollable factors existing in all work during the operation of the power station are considered, and an experience standard between the response deviation and the service life of the equipment is summarized.
Further, the standard response deviation η' is 10%.
Further, the gamma solid source is a point source.
Further, the gamma solid source is a Cs-137 source.
Further, the theoretical response data B of the tritium measuring ionization chamber in the step 3 to the gamma solid source under the current activity is calculated by adopting the following formula: b = B 0 *e -ln2/30.17*t 。
The invention has the beneficial effects that:
the technical scheme of the invention adopts a gamma solid source to replace a tritium gas source to calibrate the tritium measuring ionization chamber, and the calibration work of the tritium measuring ionization chamber can be equivalently completed after the verification of two calibration periods. The technical scheme of the invention can adopt a plurality of gamma solid sources to check and calibrate the data so as to improve the measurement accuracy.
Detailed Description
The present invention will be described in further detail with reference to specific examples.
Example 1
In view of the fact that a lot of cost is generated in the purchase process of the tritium source, project personnel develop a calibration technology for using a Cs-137 source to replace the tritium source to measure the tritium ionization chamber by combining the radioactive principle. The embodiment provides a method for calibrating a tritium measuring ionization chamber by using a gamma solid source, which sequentially comprises the following steps of:
the method comprises the following steps: and determining the standard response deviation of the tritium measuring ionization chamber to a standard tritium gas source, wherein the standard response deviation of the embodiment is not more than 10%, so that the normal measurement function of the tritium measuring ionization chamber is ensured.
Figure GDA0003895806500000041
Description of the drawings: the standard response deviation is based on big data of historical response deviation of all archived radiation monitoring equipment since the heavy water reactor unit operates, deviation trends of different types of instruments are comprehensively considered, meanwhile, uncontrollable factors existing in all work during the operation of the power station are considered, and an experience standard between the response deviation and the service life of the equipment is summarized.
Step two: and (3) responding to the tritium measurement ionization chamber by using a gamma solid source, finding out the position of the tritium measurement ionization chamber with the maximum response data to the gamma solid source, using the position as a calibration position, and marking the position by using a marking pen.
Step three: respectively recording the maximum response data of the normally functioning tritium measuring ionization chamber to a group of gamma solid sources, and calculating the slope of a curve of activity-maximum response data of the gamma solid sources as an original parameter; when two gamma solid sources are adopted, the curve is a straight line, and the slope can be directly calculated; when the number of gamma solid sources is more than two, multipoint fitting is adopted, and then the slope of a fitting straight line is calculated. The method adopts a plurality of gamma solid sources for measurement, can avoid the numerical value deviation of single group of gamma solid source radioactivity-maximum response data, and obtains more accurate calculation results as original parameters by fitting the multiple groups of data. The theoretical response data B of the tritium measuring ionization chamber to the gamma solid source under the current activity is calculated by adopting the following formula: b = B 0 *e -ln2/30.17*t 。
Step four: before calibration, calculating the radioactivity of the gamma solid source on the working day, and calculating theoretical response data of the ionization chamber to the gamma solid source under the current activity by utilizing the linear rule of the response curve of the ionization chamber to the radioactive source.
Step five: during calibration, a group of gamma solid sources are respectively arranged at calibration positions, and after response data are stable, the real response data of the tritium measuring ionization chamber to the gamma radioactive source are recorded.
Step six: and calculating the response deviation according to the theoretical response data and the real response data.
Step seven: when the response deviation is less than 10%, the calibration data of the ionization chamber can be determined to meet the expectation, and the calibration work is completed.
The gamma solid source adopted in the embodiment is a Cs-137 source, and other gamma solid sources can be selected according to the specific situation of an application place. The initial activity range of the gamma solid source is required to meet the requirement that the same type of radioactive sources with different activity levels (not less than 2 activity levels) are used as much as possible. So as to ensure the accuracy of the response curve of the ionization chamber and reduce the influence of uncertainty of the radioactive source on the whole process.
The method comprises the steps of comparing measured data of a tritium measuring analyzer and sampling results of a professional radiation protection needle cylinder of a CANDU unit within two years by using a tritium measuring ionization chamber calibrated by a gamma solid source (Cs-137 source), determining that the response deviation of the tritium measuring ionization chamber calibrated by the gamma solid source to the field tritium level is lower than 10%, wherein the calibration result meets the expectation, the calibration result of the new technology is normal, and the technology can realize the calibration of the tritium measuring ionization chamber of the CANDU unit by replacing a tritium gas source.
Example 2
The embodiment provides a method for calibrating a tritium-measuring ionization chamber by using a gamma solid source on the basis of embodiment 1, and finally selects two Cs-137 sources with different activity levels as standard sources of a new technical scheme according to a radioactive source list in a radioactive source library governed by a department to replace a tritium gas source for calibrating the tritium-measuring ionization chamber. Firstly, radioactive sources are sequentially arranged at the relative positions of the chambers of the single ionization chamber (each ionization chamber corresponds to the position of the radioactive source which responds to the maximum data), a reverse calibration method is developed and designed to eliminate activity loss generated in the long-term use process of the radioactive sources, and further, the first data acquisition is realized, and the data is used as original data to guide the calibration work of the lateral tritium ionization chamber in the future. In the calibration process, the real response data of the tritium measuring ionization chamber to the Cs-137 source is recorded, the relative error between the response data and theoretical data is calculated, when the relative error exceeds the range of 10%, the output signal of the ionization chamber is corrected by using a computer, the relative error between the response data and the theoretical data is ensured to be within the range of 10%, and therefore the calibration work is completed.
Example 3
This example further illustrates the technical solution of the present invention in combination with the selection of specific gamma solid sources on the basis of examples 1 and 2.
In a radioactive source library governed by a department, cs-137 sources with the following radioactivity activities are selected as calibration gamma solid sources. The specific information is as follows:
TABLE 1 Radioactive source information Table
Encoding Kind of radioactive source Initial activity of radioactive source (Bq) Date of production of radioactive source
Radioactive source (1) Cs-137 3.93E+4 2011.4
Radioactive source (2) Cs-137 3.26E+5 2011.4
Considering that the Cs-137 source is subject to various losses during production and use; in order to reduce theoretical data deviation caused by loss, a project group develops and designs a reverse calibration method, namely when a tritium measuring ionization chamber is initially installed and debugged, and when the relative error between the response value of the tritium measuring ionization chamber to a standard tritium gas source and the theoretical value is less than 10%, the response efficiency of the ionization chamber is considered to meet the expectation; under the working condition, the selected Cs-137 sources with different activities are placed at a top calibration position of a single ionization chamber (the position is a maximum value point of the ionization chamber responding to a radioactive source), the real responses of the ionization chamber to radioactive sources used for different range calibration at the moment are recorded, the real data of a cabinet at the moment are recorded (the material only refers to 1 calibration data of the tritium-measuring ionization chamber) and are used as a later calibration reference, wherein 2 compensation ionization chambers in the ionization chamber group generate negative value data, but the tritium-measuring ionization chamber does not theoretically display a negative value due to the setting of the display function of the tritium-measuring ionization chamber, and the minimum display value is 0MBq/m3, so that when the gamma source is used for calibrating the tritium-measuring ionization chamber, the responses of the compensation ionization chamber are not separately tested. The raw data can be referred to table 2:
TABLE 2 original data of inverse calibration method
Figure GDA0003895806500000071
The raw data recorded in table 2 were used as initial parameters, including the date of operation, and the response data of 2 measured ionization chambers in the set of ionization chambers to different sources of activity Cs-137. According to the specific time of the calibration work, taking calibration data of 11 months in 2018 as an example, the theoretical activity A1 of the radiation source (1) and the radiation source (2) on the current working day is calculated according to a radioactive decay formula, the decay coefficient between the Cs-137 source radiation source and the original data on the current working day is calculated by utilizing the linear relation of the response of the tritium-measuring ionization chamber to the gamma radiation source, the decay coefficient can be used for calculating the theoretical values B1 and C1 of the response of the tritium-measuring ionization chamber on the current working day to the Cs-137 source, meanwhile, the real response values B2 and C2 displayed by the tritium-measuring ionization chamber are recorded, and the response deviation eta is calculated through the two groups of data. And judging the working state of the tritium measuring ionization chamber by verifying whether the response deviation exceeds 10%, and if the response deviation is larger than the error range of 10%, correcting the output value by using a special computer, thereby completing the calibration work. See table 3 for calibration data.
TABLE 3 calibration data of Cs-137 solid source for tritium measurement ionization chamber
Figure GDA0003895806500000081
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. It is intended that the present invention also encompass such modifications and variations as fall within the scope of the appended claims and their equivalents.

Claims (5)

1. A method for calibrating an ionization chamber for measuring tritium by using a gamma solid source is characterized by comprising the following steps: calibrating a tritium measuring ionization chamber by using a gamma solid source to replace a standard tritium gas source;
the method sequentially comprises the following steps:
step 1, using a gamma solid source to respond to a tritium measurement ionization chamber, and finding out a position where the tritium measurement ionization chamber responds to the gamma solid source with the maximum data to serve as a calibration position;
step 2, respectively measuring the maximum response data of the tritium measuring ionization chamber to the gamma solid source by adopting two or more gamma solid sources, taking the radioactivity of the gamma solid source as a horizontal coordinate, taking the maximum response data of the tritium measuring ionization chamber to the gamma solid source as a vertical coordinate, and taking the slope of a curve as an original parameter;
step 3, calculating the radioactivity of the gamma solid source working day before calibration work, and calculating theoretical response data B of the tritium measuring ionization chamber to the gamma solid source under the current activity according to the original parameters and the radioactivity of the gamma solid source working day by utilizing the linear rule of the response curve of the tritium measuring ionization chamber to the gamma solid source;
step 4, starting to calibrate the tritium measuring ionization chamber, firstly fixing the gamma solid source at the calibration position determined in the step 1, and recording the real response data C of the tritium measuring ionization chamber to the gamma radioactive source after the response data of the tritium measuring ionization chamber to be measured are stable;
step 5, calculating response deviation eta according to the theoretical response data obtained by the calculation in the step 3 and the real response data obtained by the step 4, wherein eta = (C-B)/B100%;
step 6, when the absolute value of the response deviation eta is not greater than the standard response deviation eta', judging that the calibration data of the ionization chamber meets the expectation, thereby completing the calibration work; when the absolute value of the response deviation η is larger than the standard response deviation η ', the output value C' of the tritium measurement ionization chamber is adjusted to be consistent with the theoretical response data B, or the output value C '= (1 ± η') B of the tritium measurement ionization chamber is adjusted.
2. A method of calibrating an ionization chamber for tritium detection using a gamma solid source as claimed in claim 1, wherein: the standard response deviation η' is determined as follows:
when the service life t of the equipment is less than or equal to 5 years, the standard response deviation eta' is less than or equal to 10 percent;
t is more than or equal to 5 years, when t is less than or equal to 15 years, eta ' is less than or equal to { ROUND [ (t-3)/2 ] +10}%, eta ' of the current year and eta ' of the next year can not exceed 10% at the same time, and ROUND [ (t-3)/2 ] represents an integer for extracting [ (t-3)/2 ];
when t is more than or equal to 15 years, eta' is less than or equal to 20 percent.
3. A method of calibrating an ionization chamber for tritium detection using a gamma solid source as claimed in claim 2, wherein: the standard response deviation η' is 10%.
4. A method of calibrating a tritium measurement ionization chamber using a gamma solid source as claimed in claim 1, wherein: the gamma solid source is a point source.
5. A method of calibrating an ionization chamber for tritium detection using a gamma solid source as claimed in claim 4, wherein: the gamma solid source is a Cs-137 source, and the current radioactivity B of the gamma solid source is calculated by adopting the following formula 1 ；
B 1 ＝B 0 *e -ln2*t/30.17
Wherein, B 0 The radioactivity of the gamma solid source in the initial state, t the decay time of the gamma solid source, 30.17 is the half-life of Cs-137 in years.
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JP2000098043A (en) * 1998-09-28 2000-04-07 Toshiba Corp Nuclear fusion radiation-measuring device
CN104536028A (en) * 2015-01-15 2015-04-22 中国核动力研究设计院 On-site calibration device of airborne tritium monitoring instrument
CN107015266A (en) * 2017-05-22 2017-08-04 中国原子能科学研究院 A kind of calibration system and its scaling method of flow gas environment ion-chamber tritium concentration monitor

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59187280A (en) * 1983-04-08 1984-10-24 Asahi Chem Ind Co Ltd Continuous measurement of tritium on real time
JP2000098043A (en) * 1998-09-28 2000-04-07 Toshiba Corp Nuclear fusion radiation-measuring device
CN104536028A (en) * 2015-01-15 2015-04-22 中国核动力研究设计院 On-site calibration device of airborne tritium monitoring instrument
CN107015266A (en) * 2017-05-22 2017-08-04 中国原子能科学研究院 A kind of calibration system and its scaling method of flow gas environment ion-chamber tritium concentration monitor

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Title
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