CN113744912A - Continuous volume reduction system for solid radioactive wastes of underground nuclear power station and application method thereof - Google Patents
Continuous volume reduction system for solid radioactive wastes of underground nuclear power station and application method thereof Download PDFInfo
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- CN113744912A CN113744912A CN202110870302.4A CN202110870302A CN113744912A CN 113744912 A CN113744912 A CN 113744912A CN 202110870302 A CN202110870302 A CN 202110870302A CN 113744912 A CN113744912 A CN 113744912A
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- 239000002900 solid radioactive waste Substances 0.000 title claims abstract description 80
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 title claims abstract description 23
- 238000000034 method Methods 0.000 title claims abstract description 15
- 230000005855 radiation Effects 0.000 claims abstract description 58
- 239000007787 solid Substances 0.000 claims abstract description 7
- 230000007246 mechanism Effects 0.000 claims abstract description 4
- 230000002285 radioactive effect Effects 0.000 claims description 16
- 238000001514 detection method Methods 0.000 claims description 9
- 239000002901 radioactive waste Substances 0.000 claims description 8
- 238000005516 engineering process Methods 0.000 abstract description 2
- 239000002925 low-level radioactive waste Substances 0.000 abstract description 2
- 239000002689 soil Substances 0.000 description 15
- 238000011109 contamination Methods 0.000 description 5
- 239000000941 radioactive substance Substances 0.000 description 5
- 239000002910 solid waste Substances 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 230000007547 defect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 238000000926 separation method Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000013459 approach Methods 0.000 description 1
- 229910052788 barium Inorganic materials 0.000 description 1
- DSAJWYNOEDNPEQ-UHFFFAOYSA-N barium atom Chemical compound [Ba] DSAJWYNOEDNPEQ-UHFFFAOYSA-N 0.000 description 1
- TZCXTZWJZNENPQ-UHFFFAOYSA-L barium sulfate Chemical compound [Ba+2].[O-]S([O-])(=O)=O TZCXTZWJZNENPQ-UHFFFAOYSA-L 0.000 description 1
- 229910052601 baryte Inorganic materials 0.000 description 1
- 239000010428 baryte Substances 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005485 electric heating Methods 0.000 description 1
- 238000005265 energy consumption Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000003344 environmental pollutant Substances 0.000 description 1
- 239000006193 liquid solution Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 231100000719 pollutant Toxicity 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 239000011435 rock Substances 0.000 description 1
- 239000000523 sample Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
Abstract
The invention discloses a continuous volume reduction system for solid radioactive wastes of an underground nuclear power station, and relates to a nuclear power technology. The sorting device comprises a first-stage sorting pipe, a first branch of a second-stage sorting pipe and a second branch of the second-stage sorting pipe; a first-level radiation detector is arranged on the first-level sorting pipe; a second grade branch radiation detector is arranged on a branch of the second grade sorting pipe; a second-stage two-branch radiation detector is arranged on a second branch of the second-stage sorting pipe; the first-level sorting pipe, the first branch of the second-level sorting pipe, the second branch of the second-level sorting pipe, the first branch of the third-level sorting pipe, the second branch of the third-level sorting pipe, the fourth branch of the third-level sorting pipe and the fifth branch of the third-level sorting pipe are mechanisms capable of continuously conveying solid objects. The invention classifies the solid radioactive waste according to the radiation level, screens the low-level radioactive waste which can be discharged, and achieves the purpose of volume reduction. The invention also relates to a using method of the continuous volume reduction system for the solid radioactive wastes of the underground nuclear power station.
Description
Technical Field
The invention relates to a nuclear power technology, in particular to a continuous volume reduction system for solid radioactive wastes of an underground nuclear power station. The invention also relates to a using method of the continuous volume reduction system for the solid radioactive wastes of the underground nuclear power station.
Background
The underground nuclear power station places the nuclear-involved plant underground, utilizes the protection and containment functions of the underground rock mass to limit the release of potential radioactive substances to the environment, improves the safety of the nuclear power station, and provides a new idea for the development of nuclear power safety in China.
In order to reduce the disposal space and the transportation and disposal costs, a large-scale compressor is usually adopted to compact the solid wastes and then solidify the solid wastes in a concrete barrel or a metal barrel; this approach is reasonably feasible for a normally operating reactor with a fixed radioactive waste output.
However, after a serious accident occurs to the reactor, a large amount of radioactive substances are released, and due to the influence of radioactive contamination, the environment such as the land around the reactor also generates radioactivity, and at the moment, when radioactive contamination is decontaminated and cleaned, the soil with radioactive contamination needs to be treated as solid waste together; after a certain nuclear accident, in order to restore the environment, the Japanese government shovels out soil with the thickness of 10cm on the ground surface of a polluted area and packs and treats the polluted soil in a concentrated way, but the polluted soil is too much and can only be accumulated on a temporary placement site in a large quantity; under the condition, the prior art has the defects of small volume reduction effect, high cost, incapability of continuous and continuous operation and the like; as in the Chinese patent: the solid radioactive waste volume reduction device (application number: 201120089932.X) removes water in the solid radioactive waste by electric heating, water heating, microwave heating and other modes to achieve the purpose of volume reduction, but the scheme only removes water-containing components, has small volume reduction ratio, cannot continuously operate and has high energy consumption.
Therefore, it is necessary to develop a continuous volume reduction system for solid radioactive wastes of underground nuclear power plants.
Disclosure of Invention
The first purpose of the present invention is to overcome the defects of the background art, and provide a continuous volume reduction system for solid radioactive wastes of underground nuclear power plants.
The second purpose of the invention is to provide a use method of the solid radioactive waste continuous volume reduction system of the underground nuclear power plant.
In order to achieve the first object, the technical scheme of the invention is as follows: solid-state radioactive waste continuous volume reduction system of underground nuclear power station, its characterized in that: the sorting device comprises a primary sorting pipe, a primary sorting pipe branch and a secondary sorting pipe secondary branch, wherein one end of the primary sorting pipe is connected with a power device, and the other end of the primary sorting pipe is connected with a primary reversing valve;
one end of a branch of the second-stage sorting pipe is connected with the first-stage reversing valve, and the other end of the branch of the second-stage sorting pipe is connected with the second-stage branch reversing valve; the first-stage sorting pipe branch and the second-stage sorting pipe branch are connected with a second-stage first-stage branch reversing valve;
one end of a second branch of the second-stage sorting pipe is connected with the first-stage reversing valve, and the other end of the second branch of the second-stage sorting pipe is connected with the second-stage second-branch reversing valve; the four branches of the third-stage sorting pipe and the five branches of the third-stage sorting pipe are connected with the second-stage two-branch reversing valve;
a primary radiation detector is arranged on the primary sorting pipe, and a feedback signal of the radiation detector is connected with the power device and the primary reversing valve;
a secondary branch radiation detector is arranged on a branch of the secondary sorting pipe, and a feedback signal of the secondary branch radiation detector is connected with a secondary branch reversing valve;
a second-stage two-branch radiation detector is arranged on a second branch of the second-stage sorting pipe, and a feedback signal of the second-stage two-branch radiation detector is connected with a second-stage two-branch reversing valve;
the first-level sorting pipe, the first branch of the second-level sorting pipe, the second branch of the second-level sorting pipe, the first branch of the third-level sorting pipe, the second branch of the third-level sorting pipe, the fourth branch of the third-level sorting pipe and the fifth branch of the third-level sorting pipe are mechanisms capable of continuously conveying solid objects.
In the above technical solution, two sides of the first-stage radiation detector, the second-stage one-branch radiation detector and the second-stage two-branch radiation detector are all located between the upper shielding layer and the lower shielding layer.
In the above technical scheme, the width of the first-level sorting pipe, the first branch of the second-level sorting pipe, the second branch of the second-level sorting pipe, the first branch of the third-level sorting pipe, the second branch of the third-level sorting pipe, the fourth branch of the third-level sorting pipe and the fifth branch of the third-level sorting pipe is between 0.5cm and 50 cm.
In order to achieve the second object, the invention has the technical scheme that: a method for a continuous volume reduction system for solid radioactive waste of a nuclear underground power plant, characterized in that four radioactivity level intervals are set at A, B, C three radioactivity levels;
when the radioactivity level exceeds A, the sorted radioactive waste cannot be recycled; radioactivity level between AB can be reused after treatment; restricted use when between BC; there is no use limitation when C is less than C;
the method comprises the following steps:
step 1: the solid radioactive waste is sent to a primary radiation detector through a primary sorting pipe to detect the radioactive intensity, and a detection signal of the primary radiation detector is transmitted to a primary reversing valve; if the radioactivity level of the solid radioactive waste is greater than B, the solid radioactive waste is transferred to a first branch of the secondary sorting pipe by the primary reversing valve, and if the radioactivity level of the solid radioactive waste is less than B, the solid radioactive waste is transferred to a second branch of the secondary sorting pipe;
step 2: the solid radioactive waste is sent to a second-level branch radiation detector through a first branch of a second-level sorting pipe to detect the radioactive intensity, and a detection signal of the second-level branch radiation detector is transmitted to a second-level branch reversing valve; if the radioactivity level of the solid radioactive waste is higher than A, the second-level branch reversing valve transfers the solid radioactive waste to one third-level sorting pipe, and if the radioactivity level of the solid radioactive waste is between AB, the solid radioactive waste is transferred to the second third-level sorting pipe;
and step 3: the solid radioactive waste is sent to a second-stage second-branch radiation detector through a second branch of the second-stage sorting pipe to detect the radioactive intensity, and a detection signal of the second-stage second-branch radiation detector is transmitted to a second-stage second-branch reversing valve; if the radioactivity level of the solid radioactive waste is lower than C, the solid radioactive waste is transferred to four sorting pipes; the method achieves the aim of classifying, separating and reducing the volume according to the radioactive level of the solid radioactive waste.
Compared with the prior art, the invention has the following advantages:
1) the invention achieves the purposes of classifying and reducing the volume of the solid radioactive waste according to the radioactivity level region by subdividing the solid radioactive waste into continuous small sections, continuously intercepting one small section to monitor the radioactivity level of the small section, controlling a power device and a reversing valve through measuring signals, and transmitting the small section to different branch branches for treatment according to the radioactivity level of the small section of radioactive waste.
2) The invention can continuously run and greatly increase the processing capacity.
3) The invention classifies the solid radioactive waste according to the radiation level, screens the low-level radioactive waste which can be discharged, and achieves the purpose of volume reduction.
4) The invention can be infinitely connected in series, and realizes the fine classification of the radioactive wastes according to the actual requirements.
Drawings
FIG. 1 is a schematic structural diagram of the present invention.
Fig. 2 is a schematic diagram of the present invention.
The automatic sorting system comprises 1-first-stage sorting pipe, 11-power device, 12-first-stage reversing valve, 2-second-stage sorting pipe one branch, 21-second-stage one branch reversing valve, 22-third-stage sorting pipe one branch, 23-third-stage sorting pipe two branch, 3-second-stage sorting pipe two branch, 31-second-stage two branch reversing valve, 32-third-stage sorting pipe four branch, 33-third-stage sorting pipe five branch, 41-first-stage radiation detector, 42-second-stage one branch radiation detector, 43-second-stage two branch radiation detector, 51-upper shielding layer, 52-lower shielding layer, 61-sorting section containing radioactivity, 62-sorting section containing no radioactivity, 63-polluted soil and 64-radioactive pollutant.
Detailed Description
The embodiments of the present invention will be described in detail with reference to the accompanying drawings, which are not intended to limit the present invention, but are merely exemplary. While the advantages of the invention will be apparent and readily appreciated by the description.
With reference to the accompanying drawings: the continuous volume reduction system for the solid radioactive wastes of the underground nuclear power station comprises a primary sorting pipe 1, a secondary sorting pipe branch 2 and a secondary sorting pipe branch 3, wherein one end of the primary sorting pipe 1 is connected with a power device 11, and the other end of the primary sorting pipe is connected with a primary reversing valve 12;
one end of a first branch 2 of the second-stage sorting pipe is connected with a first-stage reversing valve 12, and the other end of the first branch is connected with a second-stage branch reversing valve 21; the first grade sorting pipe branch 22 and the second grade sorting pipe branch 23 are both connected with the second grade branch reversing valve 21;
one end of the second branch 3 of the second-stage sorting pipe is connected with the first-stage reversing valve 12, and the other end of the second branch is connected with the second-stage second-branch reversing valve 31; the fourth branch 32 of the third-level sorting pipe and the fifth branch 33 of the third-level sorting pipe are both connected with the second-level two-branch reversing valve 31;
a primary radiation detector 41 is arranged on the primary sorting pipe 1, and a feedback signal of the radiation detector 41 is connected with the power device 11 and the primary reversing valve 12;
a first branch 2 of the second-stage sorting pipe is provided with a second-stage branch radiation detector 42, and a feedback signal of the second-stage branch radiation detector 42 is connected with a second-stage branch reversing valve 21;
a second-stage second-branch radiation detector 43 is arranged on the second-stage sorting pipe second branch 3, and a feedback signal of the second-stage second-branch radiation detector 43 is connected with a second-stage second-branch reversing valve 31;
the first-level sorting pipe 1, the first branch 2 of the second-level sorting pipe, the second branch 3 of the second-level sorting pipe, the first branch 22 of the third-level sorting pipe, the second branch 23 of the third-level sorting pipe, the fourth branch 32 of the third-level sorting pipe and the fifth branch 33 of the third-level sorting pipe are mechanisms capable of continuously conveying solid objects, such as pipelines, conveying belts and the like.
The two sides of the first-stage radiation detector 41, the second-stage one-branch radiation detector 42 and the second-stage two-branch radiation detector 43 are all positioned between the upper shielding layer 51 and the lower shielding layer 52; the upper shielding layer 51 and the lower shielding layer 52 are made of materials with large atomic numbers such as lead, barium, barite and the like, and can effectively shield nuclear radiation, so that the radiation detector only detects the radiation intensity of the solid radioactive waste at the unshielded section of the pipeline between the upper shielding layer 51 and the lower shielding layer 52.
The widths of the first-level sorting pipe 1, the first branch 2 of the second-level sorting pipe, the second branch 3 of the second-level sorting pipe, the first branch 22 of the third-level sorting pipe, the second branch 23 of the third-level sorting pipe, the fourth branch 32 of the third-level sorting pipe and the fifth branch 33 of the third-level sorting pipe are 0.5cm to 50cm, and therefore the radioactive contamination nuclide distribution can be guaranteed to be concentrated as far as possible.
A method for a continuous volume reduction system for solid radioactive waste of a nuclear underground power plant, characterized in that four radioactivity level intervals are set at A, B, C three radioactivity levels;
when the radioactivity level exceeds A, the sorted radioactive waste cannot be recycled; radioactivity level between AB can be reused after treatment; restricted use when between BC; there is no use limitation when C is less than C;
the method comprises the following steps:
step 1: the solid radioactive waste is sent to a primary radiation detector 41 through a primary sorting pipe 1 to detect the radioactive intensity, and a detection signal of the primary radiation detector 41 is transmitted to a primary reversing valve 12; if the radioactivity level of the solid radioactive waste is more than B, the primary reversing valve 12 transfers the solid radioactive waste to a secondary sorting pipe branch 2, and if the radioactivity level of the solid radioactive waste is less than B, the solid radioactive waste is transferred to a secondary sorting pipe branch 3;
step 2: the solid radioactive waste is sent to the second-level branch radiation detector 42 through the second-level sorting pipe branch 2 to detect the radioactive intensity, and a detection signal of the second-level branch radiation detector 42 is transmitted to the second-level branch reversing valve 21; if the radioactivity level of the solid radioactive waste is higher than A, the second branch reversing valve 21 transfers the solid radioactive waste to the first branch 22 of the third-level sorting pipe, and if the radioactivity level of the solid radioactive waste is between AB, the solid radioactive waste is transferred to the second branch 23 of the third-level sorting pipe;
and step 3: the solid radioactive waste is sent to a second-level second-branch radiation detector 43 through a second-level sorting pipe second branch 3 to detect the radioactive intensity, and a detection signal of the second-level second-branch radiation detector 43 is transmitted to a second-level second-branch reversing valve 31; if the radioactivity level of the solid radioactive waste is between BC, the second-level two-branch reversing valve 31 transfers the solid radioactive waste to the third-level sorting pipe three-branch 32, and if the radioactivity level of the solid radioactive waste is less than C, the solid radioactive waste is transferred to the third-level sorting pipe four-branch 33; the method achieves the aim of classifying, separating and reducing the volume according to the radioactive level of the solid radioactive waste.
In practical use, in a liquid solution, solutes are uniformly distributed in the liquid, the solute distribution at any point in the liquid is the same, and solid radioactive wastes are greatly different from the solid radioactive wastes, generally, the solid radioactive wastes are nuclear contamination wastes, radionuclides fall on the solid, and the solid radioactive wastes are difficult to separate at a microscopic level, so that the solid can be treated as the solid radioactive wastes together only (the normal operation, the overhaul and the like of a nuclear power station are treated in the same way); decontamination in a typical situation such as a nuclear accident, to reduce the level of environmental radioactivity, the japanese government collects all the soil 10cm above the surface of the contaminated area "scraped" and treated as solid radioactive waste; this treatment generates about 2200 million cubes of "solid radioactive waste", placing tremendous pressure on storage, maintenance, disposal; in fact, the real radioactive substances only account for less than one ten thousandth of the substances, and the substances cannot be separated from the soil with difficulty.
If the radiation per kilogram of soil exceeds 8000 becks, the piece of soil is treated as solid radioactive waste, and the method of the Fudao is to treat the 1 kilogram of soil as the solid radioactive waste;
if the invention is used for treatment, the sorting length is 5096 cm when the diameter of the sorting pipe is 0.5cm and the effective sorting segment number is 10191 segments when the probe size of the radiation detector is 0.5cm, which are calculated by 1000 cubic centimeters per kilogram of soil volume; even in the extreme case, when 8000 becks of radioactive substance are uniformly distributed, 2191 pieces of soil containing no radioactivity are separated, i.e. the separation efficiency is 21.5%.
As shown in fig. 2, sorting segments 61 containing radioactivity are identified and sorted out, while sorting segments 62 containing no radioactivity are excluded; in practical conditions, the radioactive substance exists in the form of solid particles, the concentration degree is high, therefore, in the 10191 stage, the measuring stage with high radioactivity level appears with great probability, and the practical separation efficiency is far higher than 21.5%, namely, after 1 kg of soil solid radioactive waste is treated, the soil solid radioactive waste only has 0.215 kg of soil solid radioactive waste at most.
Other parts not described belong to the prior art.
Claims (4)
1. Solid-state radioactive waste continuous volume reduction system of underground nuclear power station, its characterized in that: the automatic sorting device comprises a primary sorting pipe (1), a secondary sorting pipe first branch (2) and a secondary sorting pipe second branch (3), wherein one end of the primary sorting pipe (1) is connected with a power device (11), and the other end of the primary sorting pipe is connected with a primary reversing valve (12);
one end of a first branch (2) of the second-stage sorting pipe is connected with a first-stage reversing valve (12), and the other end of the first branch is connected with a second-stage branch reversing valve (21); the first grade sorting pipe branch (22) and the second grade sorting pipe branch (23) are connected with a second grade branch reversing valve (21);
one end of the second branch (3) of the second-stage sorting pipe is connected with the first-stage reversing valve (12), and the other end of the second branch of the second-stage sorting pipe is connected with the second-stage second-branch reversing valve (31); the four branches (32) of the third-level sorting pipe and the five branches (33) of the third-level sorting pipe are connected with the second-level two-branch reversing valve (31);
a primary radiation detector (41) is arranged on the primary sorting pipe (1), and a feedback signal of the radiation detector (41) is connected with a power device (11) and a primary reversing valve (12);
a first-stage first-branch radiation detector (42) is arranged on the first branch (2) of the second-stage sorting pipe, and a feedback signal of the first-stage first-branch radiation detector (42) is connected with a second-stage first-branch reversing valve (21);
a second-stage two-branch radiation detector (43) is arranged on the second-stage sorting pipe second branch (3), and a feedback signal of the second-stage two-branch radiation detector (43) is connected with a second-stage two-branch reversing valve (31);
the first-level sorting pipe (1), the second-level sorting pipe first branch (2), the second-level sorting pipe second branch (3), the third-level sorting pipe first branch (22), the third-level sorting pipe second branch (23), the third-level sorting pipe fourth branch (32) and the third-level sorting pipe fifth branch (33) are mechanisms capable of continuously conveying solid objects.
2. The underground nuclear power plant solid radioactive waste continuous volume reduction system of claim 1, wherein: the two sides of the first-stage radiation detector (41), the second-stage first-branch radiation detector (42) and the second-stage second-branch radiation detector (43) are all located between the upper shielding layer (51) and the lower shielding layer (52).
3. The underground nuclear power plant solid radioactive waste continuous volume reduction system of claim 2, wherein: the width of one-level letter sorting pipe (1), second grade letter sorting pipe first branch road (2), second grade letter sorting pipe second branch road (3), tertiary letter sorting pipe one (22), tertiary letter sorting pipe two branch road (23), tertiary letter sorting pipe four branch road (32) and tertiary letter sorting pipe five branch road (33) is between 0.5cm to 50 cm.
4. A method of using the continuous volume reduction system for solid radioactive wastes of a subterranean nuclear power plant as claimed in any one of claims 1 to 2, characterized in that four radioactivity level sections are set at A, B, C three radioactivity levels;
when the radioactivity level exceeds A, the sorted radioactive waste cannot be recycled; radioactivity level between AB can be reused after treatment; restricted use when between BC; there is no use limitation when C is less than C;
the method comprises the following steps:
step 1: the solid radioactive waste is sent to a primary radiation detector (41) through a primary sorting pipe (1) to detect the radioactive intensity, and a detection signal of the primary radiation detector (41) is transmitted to a primary reversing valve (12); if the radioactivity level of the solid radioactive waste is more than B, the primary reversing valve (12) transfers the solid radioactive waste to a first branch (2) of the secondary sorting pipe, and if the radioactivity level of the solid radioactive waste is less than B, the solid radioactive waste is transferred to a second branch (3) of the secondary sorting pipe;
step 2: the solid radioactive waste is sent to a second-stage first-branch radiation detector (42) through a second-stage sorting pipe first-branch (2) to detect the radioactive intensity, and a detection signal of the second-stage first-branch radiation detector (42) is transmitted to a second-stage first-branch reversing valve (21); if the radioactivity level of the solid radioactive waste is higher than A, the second branch reversing valve (21) transfers the solid radioactive waste to the third-stage sorting pipe branch (22), and if the radioactivity level of the solid radioactive waste is between AB, the solid radioactive waste is transferred to the third-stage sorting pipe branch (23);
and step 3: the solid radioactive waste is sent to a second-level second-branch radiation detector (43) through a second-level sorting pipe second branch (3) to detect the radioactive intensity, and a detection signal of the second-level second-branch radiation detector (43) is transmitted to a second-level second-branch reversing valve (31); if the radioactivity level of the solid radioactive waste is between BC, the second-level two-branch reversing valve (31) transfers the solid radioactive waste to three-level sorting pipes (32), and if the radioactivity level of the solid radioactive waste is less than C, the solid radioactive waste is transferred to four-level sorting pipes (33); the method achieves the aim of classifying, separating and reducing the volume according to the radioactive level of the solid radioactive waste.
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Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4646978A (en) * | 1984-09-10 | 1987-03-03 | Westinghouse Electric Corp. | Method for sorting radioactive waste |
JP2004163415A (en) * | 2002-10-07 | 2004-06-10 | Kawasaki Heavy Ind Ltd | System for screening radioactive waste |
JP2013104743A (en) * | 2011-11-11 | 2013-05-30 | Mitsubishi Heavy Ind Ltd | Separating and volume reducing device for radioactive waste |
CN105665310A (en) * | 2016-03-11 | 2016-06-15 | 深圳市利美泰克自控设备有限公司 | Radioactive solid waste detecting and classifying method and system |
CN205550908U (en) * | 2016-03-11 | 2016-09-07 | 深圳市利美泰克自控设备有限公司 | Radioactive solid waste detects classification system |
US20190091730A1 (en) * | 2014-12-17 | 2019-03-28 | Envac Optibag Ab | Sorting system with multiple sorting devices |
CN110153045A (en) * | 2019-06-17 | 2019-08-23 | 博思英诺科技(北京)有限公司 | Radioactive pollution material activity continuously screens the equipment and detection method of automatic sorting |
KR102051577B1 (en) * | 2018-08-23 | 2019-12-05 | 한국원자력연구원 | Apparatus and method for treating radioactive waste |
CN215770552U (en) * | 2021-07-30 | 2022-02-08 | 长江勘测规划设计研究有限责任公司 | Continuous volume reduction system for solid radioactive wastes of underground nuclear power station |
-
2021
- 2021-07-30 CN CN202110870302.4A patent/CN113744912A/en active Pending
Patent Citations (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4646978A (en) * | 1984-09-10 | 1987-03-03 | Westinghouse Electric Corp. | Method for sorting radioactive waste |
JP2004163415A (en) * | 2002-10-07 | 2004-06-10 | Kawasaki Heavy Ind Ltd | System for screening radioactive waste |
JP2013104743A (en) * | 2011-11-11 | 2013-05-30 | Mitsubishi Heavy Ind Ltd | Separating and volume reducing device for radioactive waste |
US20190091730A1 (en) * | 2014-12-17 | 2019-03-28 | Envac Optibag Ab | Sorting system with multiple sorting devices |
CN105665310A (en) * | 2016-03-11 | 2016-06-15 | 深圳市利美泰克自控设备有限公司 | Radioactive solid waste detecting and classifying method and system |
CN205550908U (en) * | 2016-03-11 | 2016-09-07 | 深圳市利美泰克自控设备有限公司 | Radioactive solid waste detects classification system |
KR102051577B1 (en) * | 2018-08-23 | 2019-12-05 | 한국원자력연구원 | Apparatus and method for treating radioactive waste |
CN110153045A (en) * | 2019-06-17 | 2019-08-23 | 博思英诺科技(北京)有限公司 | Radioactive pollution material activity continuously screens the equipment and detection method of automatic sorting |
CN215770552U (en) * | 2021-07-30 | 2022-02-08 | 长江勘测规划设计研究有限责任公司 | Continuous volume reduction system for solid radioactive wastes of underground nuclear power station |
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