Waste source identification and filling method for waste source near-surface treatment and reconditioning

Abstract

The invention provides a waste source identifying and filling method for near-surface treatment and reconditioning of waste sources. The waste source identifying and filling method comprises the steps that the waste sources in a lead tank in a negative-pressure glove box are obtained; carrying out anti-leakage treatment on the obtained waste source; carrying out nuclide category identification on the waste source subjected to leakage prevention treatment to obtain the nuclide category of the waste source; detecting the waste source according to the nuclide category of the waste source to obtain the activity of the waste source; and filling the waste source according to the activity of the waste source. According to the scheme, an operator can be prevented from directly looking at the waste source when identifying and filling the waste source, and the exposure dose of the operator is prevented from being increased; and meanwhile, the conditions of waste source cladding damage and radioactive contamination leakage can be avoided.

Description

Technical Field

[0001] The invention relates to the technical field of waste source near-surface disposal, and in particular to a waste source identification and filling method for waste source near-surface disposal preparation. Background Art

[0002] Currently, there is no overall technical method for the identification and filling of waste sources before packaging. When identifying and filling waste sources, operators need to look directly at the waste sources, which increases the exposure dose to the operators. At the same time, during the operation, the damage of the waste source cladding and the leakage of radioactive contamination are not taken into account. Summary of the invention

[0003] The present invention provides a method for identifying and filling waste sources in the preparation of near-surface disposal of waste sources, which can avoid operators from directly looking at the waste sources when identifying and filling the waste sources, thereby avoiding an increase in the exposure dose of the operators; and at the same time, can avoid damage to the waste source cladding and leakage of radioactive contamination.

[0004] In order to solve the above technical problems, the technical solution of the present invention is as follows:

[0005] A method for identifying and filling waste sources for near-surface disposal of waste sources, comprising:

[0006] Obtain the waste source inside the lead tank in the negative pressure glove box;

[0007] Carry out leakage prevention treatment on the acquired waste sources;

[0008] Identify the nuclide category of the waste source that has completed the leakage prevention treatment to obtain the nuclide category of the waste source;

[0009] Detect the waste source according to its nuclide type and obtain its activity;

[0010] The waste sources are charged and processed according to their activity.

[0011] Optionally, the waste sources in the lead cans in the negative pressure glove box are packed in the lead cans by using a clamping tool to separate the waste sources in the centralized container.

[0012] Optionally, obtaining the waste source inside the lead tank in the negative pressure glove box includes:

[0013] The location of the waste source inside the lead tank is collected through the endoscope inside the negative pressure glove box, and the waste source inside the lead tank is clamped by the clamp matched with the endoscope to obtain it.

[0014] Optionally, the obtained waste source is subjected to leakage prevention treatment, including:

[0015] Placing the obtained waste source in a liquid film container in the negative pressure glove box, so that the waste source is dipped into the liquid film;

[0016] Wrap aluminum foil around the outside of the waste source dipped in the liquid film;

[0017] The waste source wrapped in aluminum foil is placed in a tray in the negative pressure glove box to complete the leakage prevention treatment.

[0018] Optionally, the waste source that has completed the anti-leakage treatment is identified by the nuclide category to obtain the nuclide category of the waste source, including:

[0019] Detecting and analyzing the waste sources in the tray by using a gamma spectrometer to obtain the nuclide category of the waste sources;

[0020] The nuclide categories include gamma sources, alpha sources and beta sources.

[0021] Optionally, the waste source is tested according to the nuclide type of the waste source to obtain the activity of the waste source, including:

[0022] Detecting the gamma dose rate of the waste source whose nuclide type is a gamma source by a gamma spectrometer, wherein the gamma spectrometer and the tray are located on both sides of the lead brick, and the detection distance between the gamma spectrometer and the waste source whose nuclide type is a gamma source is 30 cm;

[0023] According to the gamma dose, the activity of the spent source whose nuclide type is a gamma source is obtained by a first formula.

[0024] Optionally, according to the gamma dose, the activity of the spent source whose nuclide type is a gamma source is obtained by a first formula, including:

[0025] By the first formula:

[0026]

[0027] Obtain the activity of the spent source whose nuclide type is γ source;

[0028] Where A represents activity (Bq); represents the gamma dose rate (μSv / h); Γk represents the air kerma rate constant (Gy·m 2 ·Bq -1 ·s -1 );d1 represents the thickness of the lead brick; d f1 It is the semi-shielding thickness of the shielding material for the nuclide.

[0029] Optionally, the waste source is tested according to the nuclide type of the waste source to obtain the activity of the waste source, which also includes:

[0030] Detection counts of waste sources of the nuclide type α source or β source are detected by a surface contamination monitor, wherein the distance between the surface contamination monitor and the waste source of the α source or β source is 5 mm;

[0031] According to the detection counts, the activity of the spent source whose nuclide category is α source or β source is obtained by a second formula.

[0032] Optionally, according to the detection count, the activity of the spent source whose nuclide category is an alpha source or a beta source is obtained by a second formula, including:

[0033] According to the second formula:

[0034]

[0035] Obtain the activity of the spent source whose nuclide type is α source or β source;

[0036] Where A represents activity (Bq); Count represents detection counts (cps); S1 represents source effective area; S0 represents instrument detection area; and η represents instrument detection efficiency.

[0037] Optionally, the spent source is charged according to its activity, including:

[0038] If the activity of the waste source meets the packaging activity requirement, the waste source is placed in the lower source pipeline on the bottom surface of the negative pressure glove box by a clamp, and the waste source is introduced into the packaging tube through the lower source pipeline.

[0039] The above solution of the present invention includes at least the following beneficial effects:

[0040] The above scheme of the present invention obtains the waste source inside the lead can in the negative pressure glove box; performs leakage prevention treatment on the obtained waste source; performs radionuclide classification identification on the waste source that has completed the leakage prevention treatment to obtain the radionuclide classification of the waste source; detects the waste source according to the radionuclide classification of the waste source to obtain the activity of the waste source; and performs loading treatment on the waste source according to the activity of the waste source; this can avoid the operator from directly looking at the waste source when identifying and loading the waste source, thereby avoiding an increase in the exposure dose of the operator; and at the same time, it can avoid the damage of the waste source cladding and the leakage of radioactive contamination. BRIEF DESCRIPTION OF THE DRAWINGS

[0041] Figure 1 It is a flow chart of a method for identifying and loading waste sources for near-surface disposal of waste sources provided by an embodiment of the present invention;

[0042] Figure 2 A schematic diagram of the internal layout of the negative pressure glove box of the present invention. DETAILED DESCRIPTION

[0043] The exemplary embodiments of the present invention will be described in more detail below with reference to the accompanying drawings. Although the exemplary embodiments of the present invention are shown in the accompanying drawings, it should be understood that the present invention can be implemented in various forms and should not be limited by the embodiments set forth herein. On the contrary, these embodiments are provided in order to enable a more thorough understanding of the present invention and to enable the scope of the present invention to be fully communicated to those skilled in the art.

[0044] like Figure 1 As shown, an embodiment of the present invention provides a method for identifying and filling waste sources for near-surface disposal of waste sources, comprising:

[0045] Step 11, obtaining the waste source inside the lead tank 21 in the negative pressure glove box 20;

[0046] Step 12, performing leakage prevention treatment on the obtained waste source;

[0047] Step 13, performing nuclide classification on the waste source that has completed the anti-leakage treatment to obtain the nuclide classification of the waste source;

[0048] Step 14, detecting the waste source according to the nuclide type of the waste source to obtain the activity of the waste source;

[0049] Step 15, loading and processing the waste source according to the activity of the waste source.

[0050] In this embodiment, the waste source inside the lead tank 21 in the negative pressure glove box 20 is obtained; the obtained waste source is subjected to leakage prevention treatment; the nuclide category of the waste source that has completed the leakage prevention treatment is identified to obtain the nuclide category of the waste source; the waste source is tested according to the nuclide category of the waste source to obtain the activity of the waste source; the waste source is loaded according to the activity of the waste source; by completing the identification and loading of the waste source in the negative pressure glove box 20, it is possible to avoid the operator directly looking at the waste source when identifying and loading the waste source, thereby avoiding an increase in the exposure dose of the operator; and at the same time, it is possible to avoid the damage of the waste source cladding and the leakage of radioactive contamination.

[0051] In an optional embodiment of the present invention, the waste sources in the lead tank 21 in the negative pressure glove box 20 are packed into the lead tank 21 by a clamping tool to separate the waste sources in the centralized container.

[0052] In this embodiment, when the size and weight of the centralized container meet the requirements for being directly transported into the negative pressure glove box 20, the centralized container can be directly transferred into the negative pressure glove box 20;

[0053] When the size and weight of the centralized container meet the requirements for being directly delivered to the negative pressure glove box 20, the waste sources in the centralized container are divided into lead cans 21 through a clamping tool, and the lead cans 21 containing the divided waste sources are transferred to the negative pressure glove box 20. After the operator puts on protective equipment such as lead clothing, subsequent operations are performed in the negative pressure glove box 20 to avoid the operator from identifying the waste sources and looking directly at the waste sources when filling them, thereby avoiding an increase in the operator's radiation dose.

[0054] In an optional embodiment of the present invention, step 11 includes:

[0055] Step 111 , the position of the waste source inside the lead tank 21 is collected through the endoscope 23 inside the negative pressure glove box 20 , and the waste source inside the lead tank 21 is clamped by the clamp matched with the endoscope 23 .

[0056] In this embodiment, a clamp for clamping the waste source is provided in the tool tray 27 in the negative pressure glove box 20; the display part of the endoscope 23 is located outside the negative pressure glove box 20, and the probe 231 of the endoscope 23 corresponds to the interior of the lead tank 21. The endoscope 23 is convenient for the operator to collect the position of the waste source inside the lead tank 21, so that the operator can accurately clamp the waste source in the lead tank 21. The operation is simple and convenient, which helps to improve the operating efficiency and help to avoid an increase in the exposure dose of the operator.

[0057] In an optional embodiment of the present invention, step 12 includes:

[0058] Step 121, placing the obtained waste source in the liquid film container 24 in the negative pressure glove box 20, so that the waste source is dipped in the liquid film;

[0059] Step 122, wrapping aluminum foil around the waste source dipped in the liquid film;

[0060] Step 123, placing the waste source wrapped in aluminum foil in the tray 25 in the negative pressure glove box 20 to complete the anti-leakage treatment.

[0061] In this embodiment, the obtained waste source is placed in a liquid membrane container 24, so that the waste source is dipped in the liquid membrane, a protective film is formed on the surface of the waste source by the liquid membrane, and aluminum foil is wrapped on the outside of the waste source to complete the leakage prevention treatment of the waste source, which can avoid damage to the waste source shell and leakage of radioactive contamination; the position of the tray 25 is observed in conjunction with the reflector 22 inside the negative pressure glove box 20, and the waste source wrapped in aluminum foil is placed in the tray 25 inside the negative pressure glove box 20, so as to facilitate the subsequent identification of the waste source.

[0062] In an optional embodiment of the present invention, step 13 includes:

[0063] Step 131, using a gamma spectrometer 29 to detect and analyze the waste sources in the tray 25 to obtain the nuclide type of the waste sources;

[0064] The nuclide categories include gamma sources, alpha sources and beta sources.

[0065] In this embodiment, the nuclide types of the waste sources in the analysis tray 25 are detected by a gamma spectrometer 29 in the negative pressure glove box 20 to identify the nuclide types of the waste sources, thereby facilitating subsequent corresponding detection according to the nuclide types of the waste sources, so as to obtain the activity of the waste sources.

[0066] In an optional embodiment of the present invention, step 14 includes:

[0067] Step 141, detecting the gamma dose rate of the waste source whose nuclide type is a gamma source by using a gamma spectrometer 29, wherein the gamma spectrometer 29 and the tray 25 are located on both sides of the lead brick 26, and the detection distance between the gamma spectrometer 29 and the waste source whose nuclide type is a gamma source is 30 cm;

[0068] Step 142, according to the gamma dose, obtain the activity of the spent source whose nuclide type is a gamma source by using a first formula;

[0069] Further, step 142 includes:

[0070] By the first formula:

[0071]

[0072] Obtain the activity of the spent source whose nuclide type is γ source;

[0073] Where A represents activity (Bq); represents the gamma dose rate (μSv / h); Γk represents the air kerma rate constant (Gy·m 2 ·Bq -1 ·s -1 );d1 represents the thickness of the lead brick; d f1 It is the semi-shielding thickness of the shielding material for the nuclide.

[0074] In this embodiment, when the nuclide type of the waste source is a γ source, the γ spectrometer 29 is moved to one side of the lead brick 26, so that the γ spectrometer 29 and the tray 25 are located on both sides of the lead brick 26, and the detection distance between the γ spectrometer 29 and the waste source of the nuclide type is a γ source is 30 cm; the γ dose rate of the waste source of the nuclide type is a γ source is measured by the γ spectrometer 29; The activity of the waste source whose nuclide category is γ source is obtained; the overall operation is simple, and the activity of the waste source whose nuclide category is γ source can be obtained quickly, so that the activity of the waste source can be reviewed, and the waste source can be loaded and processed according to the activity of the waste source;

[0075] In this embodiment, the waste sources are Co-60 source and Cs-137 source as examples. f1The value is 1.2cm; the d of Cs-137 f1 The value is 0.65cm.

[0076] In an optional embodiment of the present invention, step 14 further includes:

[0077] Step 143, detecting the detection count of the waste source whose nuclide type is α source or β source by the surface contamination monitor 28, wherein the distance between the surface contamination monitor 28 and the waste source of α source or β source is 5 mm;

[0078] Step 144, according to the detection count, obtain the activity of the spent source whose nuclide category is α source or β source by a second formula;

[0079] Further, step 144 includes:

[0080] According to the second formula:

[0081]

[0082] Obtain the activity of the spent source whose nuclide type is α source or β source;

[0083] Where A represents activity (Bq); Count represents detection counts (cps); S1 represents source effective area; S0 represents instrument detection area; and η represents instrument detection efficiency.

[0084] In this embodiment, when the nuclide type of the waste source is an α source or a β source, the surface contamination monitor 28 is placed close to the α source or the β source for detection, and the distance between the surface contamination monitor 28 and the waste source of the α source or the β source is 5 mm; the detection count of the waste source of the α source or the β source is detected by the surface contamination monitor 28;

[0085] pass The activity of the waste source whose nuclide category is α source or β source is obtained; the overall operation is simple, and the activity of the waste source whose nuclide category is α source or β source can be quickly obtained, which is convenient for reviewing the activity of the waste source, so as to charge and process the waste source according to the activity of the waste source;

[0086] In this embodiment, taking the Sr-90 source as an example, the value of η of the α source is 0.51; the value of η of the β source is 0.62.

[0087] In an optional embodiment of the present invention, step 15 includes:

[0088] If the activity of the waste source meets the packaging activity requirement, the waste source is placed in the lower source pipeline 201 on the bottom surface of the negative pressure glove box 20 by a clamp, and the waste source is introduced into the packaging tube through the lower source pipeline 201.

[0089] In this embodiment, before the operation, the packaging tube is placed inside the shielding container below the negative pressure glove box 20, and the upper end opening of the packaging tube corresponds to the lower source pipeline 201 on the bottom surface of the negative pressure glove box 20;

[0090] If the activity of the waste source meets the packaging activity requirement, the waste source is placed in the lower source pipeline 201 on the bottom surface of the negative pressure glove box 20 by a fixture, and the waste source is introduced into the packaging tube through the lower source pipeline 201 to achieve the filling of the waste source;

[0091] When the cumulative activity reaches the single nuclide packaging limit or the surface dose level of the lead tank 21 detected by the gamma spectrometer 29 is close to 2mSv / h, stop loading the waste source and shake the packaging tube slightly to make the waste source stack more compact;

[0092] If the inactivity of the waste source meets the packaging activity requirements, the waste source will be temporarily stored in a temporary shielding container in the negative pressure glove box 20. After other waste sources whose activities meet the packaging activity requirements are loaded, the waste sources whose activities do not meet the packaging activity requirements will be transferred to the centralized container for storage.

[0093] Waste source near surface disposal preparation Waste source identification and filling process:

[0094] The waste sources in the centralized container are divided into lead cans 21 by a clamping tool, and the lead cans 21 containing the divided waste sources are transferred into the negative pressure glove box 20;

[0095] The waste source position inside the lead tank 21 is collected by the endoscope 23 inside the negative pressure glove box 20, and the waste source inside the lead tank 21 is clamped by the clamp matched with the endoscope 23;

[0096] The obtained waste source is placed in the liquid film container 24 in the negative pressure glove box 20, so that the waste source is dipped in the liquid film, aluminum foil is wrapped around the outside of the waste source dipped in the liquid film, and the waste source wrapped in aluminum foil is placed in the tray 25 in the negative pressure glove box 20 to complete the leakage prevention treatment;

[0097] The waste source in the tray 25 is detected and analyzed by a gamma spectrometer 29 to obtain the nuclide type of the waste source;

[0098] When the nuclide type of the waste source is a γ source, the γ dose rate of the waste source of the nuclide type of the γ source is detected by the γ spectrometer 29, and according to the γ dose, the formula is The activity of the spent source whose nuclide category is γ source is obtained; the detection count of the spent source whose nuclide category is α source or β source is detected by the surface contamination monitor 28, and the Obtain the activity of the spent source whose nuclide type is α source or β source;

[0099] If the activity of the waste source meets the packaging activity requirement, the waste source is placed on the lower source pipe 201 on the bottom surface of the negative pressure glove box 20 by a clamp, and the waste source is introduced into the packaging tube through the lower source pipe 201 to realize the filling of the waste source; when the cumulative activity reaches the packaging limit of a single nuclide or the surface dose level of the lead tank 21 detected by the gamma spectrometer 29 is close to 2mSv / h, the filling of the waste source is stopped, and the packaging tube is slightly shaken to make the waste source stacked more compactly; if the inactivity of the waste source meets the packaging activity requirement, the waste source is temporarily stored in a temporary storage shielding container in the negative pressure glove box 20, and after other waste sources whose activities meet the packaging activity requirements are completed, the waste sources whose activities do not meet the packaging activity requirements are transferred to the centralized container for storage.

[0100] The above-mentioned embodiment of the present invention provides a method for identifying and loading waste sources for near-surface disposal of waste sources. By encapsulating the waste source in a lead can 21 and placing the lead can 21 in a negative pressure glove box 20, the space for subsequent waste source clamping inside the negative pressure glove box 20 and waste source identification is increased, which greatly shortens the operation time of a single waste source inside the negative pressure glove box 20, thereby reducing the radiation dose to personnel. The waste source is clamped by the endoscope 23 and the reflector 22 inside the negative pressure glove box 20, and the clamps and manual clamps matching the endoscope 23 are used. On the one hand, it solves the problem that the waste source is located in the corner of the lead can 21 and is difficult to be manually clamped inside the negative pressure glove box 20. On the other hand, the endoscope 23 and the negative pressure glove box 20 are used to clamp the waste source. The reflector 22 inside the negative pressure glove box 20 reduces the area of ​​personnel exposed to radiation, greatly reducing the radiation dose of personnel; the waste source taken out from the lead tank 21 is immediately dipped in the liquid film placed in the negative pressure glove box 20, and then placed on the tray 25 and wrapped with aluminum foil to prevent possible leakage sources from contaminating the equipment; the current activity of the waste source is confirmed by measuring the gamma dose rate or the surface α / β count rate; after a waste source is identified, the fixture set inside the negative pressure glove box 20 is used to automatically slide the waste source from the lower source pipe 201 into the waste source packaging tube with a shielding effect, reducing the radiation dose of personnel and optimizing the loading process of the waste source.

[0101] The above is a preferred embodiment of the present invention. It should be pointed out that for ordinary technicians in this technical field, several improvements and modifications can be made without departing from the principles of the present invention. These improvements and modifications should also be regarded as the scope of protection of the present invention.

Claims

1. A method for identifying and filling waste sources for near-surface disposal of waste sources, characterized in that: include: Obtain the waste source inside the lead tank in the negative pressure glove box; Carry out leakage prevention treatment on the acquired waste sources; Identify the nuclide category of the waste source that has completed the leakage prevention treatment to obtain the nuclide category of the waste source; Detect the waste source according to its nuclide type and obtain its activity; The waste sources are charged and processed according to their activity.

2. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 1 is characterized in that: The waste sources in the lead cans in the negative pressure glove box are packed in the lead cans by using a clamping tool to separate the waste sources in the centralized container.

3. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 1 is characterized in that: Obtain the waste sources inside the lead tank in the negative pressure glove box, including: The location of the waste source inside the lead tank is collected through the endoscope inside the negative pressure glove box, and the waste source inside the lead tank is clamped by the clamp matched with the endoscope to obtain it.

4. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 1, characterized in that: The acquired waste sources shall be treated in a leak-proof manner, including: Placing the obtained waste source in a liquid film container in the negative pressure glove box, so that the waste source is dipped into the liquid film; Wrap aluminum foil around the outside of the waste source dipped in the liquid film; The waste source wrapped in aluminum foil is placed in a tray in the negative pressure glove box to complete the leakage prevention treatment.

5. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 4 is characterized in that: The waste sources that have completed the leakage prevention treatment are identified by the nuclide category, and the nuclide category of the waste sources is obtained, including: Detecting and analyzing the waste sources in the tray by using a gamma spectrometer to obtain the nuclide category of the waste sources; The nuclide categories include gamma sources, alpha sources and beta sources.

6. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 5, characterized in that: The waste source is tested according to its nuclide type to obtain the activity of the waste source, including: Detecting the gamma dose rate of the waste source whose nuclide type is a gamma source by a gamma spectrometer, wherein the gamma spectrometer and the tray are located on both sides of the lead brick, and the detection distance between the gamma spectrometer and the waste source whose nuclide type is a gamma source is 30 cm; According to the gamma dose, the activity of the spent source whose nuclide type is a gamma source is obtained by a first formula.

7. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 6, characterized in that: According to the gamma dose, the activity of the spent source whose nuclide type is a gamma source is obtained by a first formula, including: By the first formula: Obtain the activity of the spent source whose nuclide type is γ source; Where A represents activity; represents the gamma dose rate; Γk represents the air kerma rate constant; d1 represents the thickness of the lead brick; d f1 It is the semi-shielding thickness of the shielding material for the nuclide.

8. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 5, characterized in that: The waste source is tested according to its nuclide type to obtain the activity of the waste source, which also includes: Detection counts of waste sources of the nuclide type α source or β source are detected by a surface contamination monitor, wherein the distance between the surface contamination monitor and the waste source of the α source or β source is 5 mm; According to the detection counts, the activity of the spent source whose nuclide category is α source or β source is obtained by a second formula.

9. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 8, characterized in that: According to the detection count, the activity of the spent source whose nuclide category is α source or β source is obtained by a second formula, including: According to the second formula: Obtain the activity of the spent source whose nuclide type is α source or β source; Where A represents activity; Count represents detection count; S1 represents source effective area; S0 represents instrument detection area; and η represents instrument detection efficiency.

10. The method for identifying and filling waste sources for near-surface disposal of waste sources according to claim 1, characterized in that: The waste sources are filled and processed according to their activity, including: If the activity of the waste source meets the packaging activity requirement, the waste source is placed in the lower source pipeline on the bottom surface of the negative pressure glove box by a clamp, and the waste source is introduced into the packaging tube through the lower source pipeline.

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