CN106935292B - A kind of method of a variety of enriched uranium pellet column lengths in measurement nuclear fuel rod - Google Patents
A kind of method of a variety of enriched uranium pellet column lengths in measurement nuclear fuel rod Download PDFInfo
- Publication number
- CN106935292B CN106935292B CN201511028992.XA CN201511028992A CN106935292B CN 106935292 B CN106935292 B CN 106935292B CN 201511028992 A CN201511028992 A CN 201511028992A CN 106935292 B CN106935292 B CN 106935292B
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- length
- column
- pellets
- fuel rod
- natural uranium
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- 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
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention belongs to fuel assembly technical fields, and in particular to a method of measuring a variety of enriched uranium pellet column lengths in nuclear fuel rod.The method of the present invention, specifically includes following steps：Master bar is made, γ count values are measured, data fitting is actually detected.The present invention solves the technical issues of existing detection method can not detect natural uranium pellet column length.By using gamma-rays spectral measurement method, the measurement of natural uranium pellet column length is realized, solves the problems, such as that γ absorption processes are unable to measure, meets the measurement request of natural uranium pellet column length in TVS-2M fuel rods.
Description
Technical field
The invention belongs to fuel assembly technical fields, and in particular to a variety of enriched uranium column of pellets in a kind of measurement nuclear fuel rod
The method of length.
Background technology
In novel fuel assembly, it is desirable that two ends of enriched uranium column of pellets load the day of certain length in its fuel rod
Right uranium pellet, and the clear stipulaties length of column of pellets in the technology requirement.Therefore it is needed in the manufacturing process of fuel rod
100% its assembling quality of inspection and the length for measuring natural uranium column of pellets.Original measurement method gamma-rays absorption process can
To detect the length of whole column of pellets in fuel rod, but different degree of enrichment or a variety of enriched uranium regions in fuel rod cannot be distinguished out
Pellet column length, the absorption coefficient of different degree of enrichment pellets is the same for gamma-rays absorption process, therefore, the party
Method can not tell the column of pellets of natural uranium pellet and enriched uranium uranium pellet, cannot also detect natural uranium pellet in fuel rod
The length of column.
Invention content
The technical problem to be solved in the invention is：Existing detection method can not detect the length of natural uranium column of pellets
Degree.
The method of the present invention, specifically includes following steps：
Step 1 makes master bar
The natural uranium pellet and enriched uranium pellet pellet of selection standard length, manufacture several standard fuel rods, Mei Gebiao
Known to the physical length of the natural uranium column of pellets of reference standard fuel stick.
Step 2 measures γ count values
Using γ counting devices, each standard fuel rod is allowed, by γ counting devices, to obtain each mark with constant speed
The γ count values of the natural uranium column of pellets of reference standard fuel stick.
Step 3, data fitting
Value Data is counted according to the length data of each natural uranium column of pellets and γ, fits the length of natural uranium column of pellets
Have with the relationship of γ count values as follows：
N=a × L+b
Wherein, N is γ count values, and L is the length of natural uranium column of pellets, and a is constant coefficient, and b is constant, and a and b pass through data
Fitting obtains.
It is step 4, actually detected
By fuel rod to be detected again with identical constant speed by γ counting devices, fuel rod to be detected is obtained
γ count values use the formula fitted in step 3, you can calculate the length of natural uranium column of pellets in fuel rod to be detected
Degree.
Beneficial effects of the present invention are：
The present invention realizes the measurement of natural uranium pellet column length, solves by using gamma-rays spectral measurement method
The problem that γ absorption processes are unable to measure meets the measurement request of natural uranium pellet column length in TVS-2M fuel rods.
Description of the drawings
Fig. 1 is standard fuel rod structural schematic diagram.
Specific implementation mode
This send out a kind of measure nuclear fuel rod in a variety of enriched uranium pellet column lengths method, design and manufactured such as Fig. 1 institutes
The master bar of natural uranium pellet column length in the TVS-2M fuel rods shown loads the natural of different length in a variety of master bars
Uranium pellet can be distinguished in different enriched uranium pellets using gamma-ray spectrometry and release gamma intensity, according to gamma-rays
The difference of intensity finds out not same core automatically to distinguish different enriched uranium pellet columnar regions by the progress of the computer software of exploitation
The γ count values of block columnar region.The data that the natural uranium column of pellets of different length in master bar is measured, can by curve matching
To obtain curvilinear equation, as long as the γ count values that the count value measured in tested fuel rod is measured with master bar are compared
Compared with, so that it may to measure some region of natural uranium pellet column length.
Specifically include following steps：
Step 1 makes master bar
The natural uranium pellet and enriched uranium pellet pellet of selection standard length, manufacture several standard fuel rods, Mei Gebiao
Known to the physical length of the natural uranium column of pellets of reference standard fuel stick.
Step 2 measures γ count values
Using γ counting devices, each standard fuel rod is allowed, by γ counting devices, to obtain each mark with constant speed
The γ count values of the natural uranium column of pellets of reference standard fuel stick.
Step 3, data fitting
Value Data is counted according to the length data of each natural uranium column of pellets and γ, fits the length of natural uranium column of pellets
Have with the relationship of γ count values as follows：
N=a × L+b
Wherein, N is γ count values, and L is the length of natural uranium column of pellets, and a is constant coefficient, and b is constant.
It is step 4, actually detected
By fuel rod to be detected again with identical constant speed by γ counting devices, fuel rod to be detected is obtained
γ count values use the formula fitted in step 3, you can calculate the length of natural uranium column of pellets in fuel rod to be detected
Degree.
It is the detection method of natural uranium pellet column length recorded in above-mentioned steps, method of the invention can be also used for
The length of other different degree of enrichment uranium column of pellets is detected, the degree of enrichment of other concentration of full-length need to will be only packed into master bar
Uranium pellet fits the relationship of the length and γ count values of the degree of enrichment uranium pellet of other concentration.
It is as shown in table 1 below to the measurement result of one group of fuel rod using the method for the present invention：
Table 1：Natural uranium pellet column length measurement result in master bar
Can be seen that from the measurement result of table 1 can accurately detect TVS-2M fuel rods using gamma-ray spectrometry
The length of top and bottom natural uranium column of pellets, device measuring precision meet the technology requirement of its measurement, solve gamma-rays suction
The undetectable problem of receipts method.
Claims (1)
1. a kind of method measuring a variety of enriched uranium pellet column lengths in nuclear fuel rod, which is characterized in that include the following steps：
Specifically include following steps：
Step 1 makes master bar
The natural uranium pellet and enriched uranium pellet pellet of selection standard length manufacture several standard fuel rods, each standard combustion
Known to the physical length of the natural uranium column of pellets of charge bar；
Step 2 measures γ count values
Using γ counting devices, each standard fuel rod is allowed, by γ counting devices, to obtain each standard combustion with constant speed
The γ count values of the natural uranium column of pellets of charge bar；
Step 3, data fitting
Value Data is counted according to the length data of each natural uranium column of pellets and γ, fits the length and γ of natural uranium column of pellets
The relationship of count value has as follows：
N=a × L+b
Wherein, N is γ count values, and L is the length of natural uranium column of pellets, and a is constant coefficient, and b is constant, and a and b are fitted by data
It obtains；
It is step 4, actually detected
By fuel rod to be detected again with identical constant speed by γ counting devices, the γ meters of fuel rod to be detected are obtained
Numerical value uses the formula fitted in step 3, you can calculates the length of natural uranium column of pellets in fuel rod to be detected.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201511028992.XA CN106935292B (en) | 2015-12-31 | 2015-12-31 | A kind of method of a variety of enriched uranium pellet column lengths in measurement nuclear fuel rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201511028992.XA CN106935292B (en) | 2015-12-31 | 2015-12-31 | A kind of method of a variety of enriched uranium pellet column lengths in measurement nuclear fuel rod |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106935292A CN106935292A (en) | 2017-07-07 |
| CN106935292B true CN106935292B (en) | 2018-11-02 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201511028992.XA Active CN106935292B (en) | 2015-12-31 | 2015-12-31 | A kind of method of a variety of enriched uranium pellet column lengths in measurement nuclear fuel rod |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106935292B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110853775B (en) * | 2019-11-21 | 2021-05-14 | 中国核动力研究设计院 | Multi-type fuel assembly mixed loading metal cooling reactor and management method |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4822552A (en) * | 1987-02-25 | 1989-04-18 | Westinghouse Electric Corp. | Method and apparatus for passively gamma scanning a nuclear fuel rod |
| US4902467A (en) * | 1988-08-31 | 1990-02-20 | General Electric Company | Non-destructive testing of nuclear fuel rods |
| JP2010151696A (en) * | 2008-12-26 | 2010-07-08 | Toshiba Corp | Device and method for measuring burnup |
| CN103837434A (en) * | 2012-11-20 | 2014-06-04 | 中核建中核燃料元件有限公司 | Integrated apparatus used for measuring geometric density of uranium dioxide fuel pellet |
-
2015
- 2015-12-31 CN CN201511028992.XA patent/CN106935292B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4822552A (en) * | 1987-02-25 | 1989-04-18 | Westinghouse Electric Corp. | Method and apparatus for passively gamma scanning a nuclear fuel rod |
| US4902467A (en) * | 1988-08-31 | 1990-02-20 | General Electric Company | Non-destructive testing of nuclear fuel rods |
| JP2010151696A (en) * | 2008-12-26 | 2010-07-08 | Toshiba Corp | Device and method for measuring burnup |
| CN103837434A (en) * | 2012-11-20 | 2014-06-04 | 中核建中核燃料元件有限公司 | Integrated apparatus used for measuring geometric density of uranium dioxide fuel pellet |
Non-Patent Citations (1)
| Title |
|---|
| 用γ扫描测量相对燃耗分布;张肇源 等;《核科学与工程》;19830301;第3卷(第1期);第93-96页 * |
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| CN106935292A (en) | 2017-07-07 |
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