CN213545930U - A bushing apparatus for on-line monitoring post-treatment plant pulse extraction post plutonium concentration - Google Patents
A bushing apparatus for on-line monitoring post-treatment plant pulse extraction post plutonium concentration Download PDFInfo
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- CN213545930U CN213545930U CN202021750634.6U CN202021750634U CN213545930U CN 213545930 U CN213545930 U CN 213545930U CN 202021750634 U CN202021750634 U CN 202021750634U CN 213545930 U CN213545930 U CN 213545930U
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- 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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Abstract
The utility model belongs to the technical field of the spent fuel aftertreatment, concretely relates to a bushing apparatus that is used for pulse extraction post plutonium concentration of on-line monitoring aftertreatment factory. The device is used for placing a series detection device, the series detection device is formed by connecting a plurality of neutron detectors (7) in series through cables (8), the sleeve device comprises an elbow (2) and a straight pipe (3) which are connected through a reducer head (6), and the series detection device can pass through the elbow (2) to enter and exit the straight pipe (3). The utility model discloses can make neutron detector (7) measure the plutonium solution of each plate section of pulse extraction post (1) to in time reflect the situation of change of solution concentration, reached on-line monitoring's purpose, when solution concentration takes place unusually, can in time discover and adjust, thereby prevent the accident, also can regard as an important technological means of critical safety monitoring simultaneously. The worker can replace the neutron detector (7) without entering the equipment room, and the radiation danger is reduced.
Description
Technical Field
The utility model belongs to the technical field of the spent fuel aftertreatment, concretely relates to a bushing apparatus that is used for pulse extraction post plutonium concentration of on-line monitoring aftertreatment factory.
Background
Spent fuel, also known as irradiated nuclear fuel, is spent nuclear fuel that has been subjected to irradiation, typically produced by a nuclear reactor in a nuclear power plant. From 3% to 4% of the uranium waste (spent fuel) that has been used, uranium and plutonium are chemically separated from the fission products, a technique known as spent fuel redissolution and reprocessing. The recovered uranium and plutonium can be recycled in the mixed oxide fuel of the nuclear power plant to produce more energy, thereby enabling the uranium resources to be more fully utilized and reducing the concentration requirements. Post-processing also aids in the final disposal of the waste by reducing the volume of the high level waste and removing plutonium.
The commonly used solvent extraction equipment with good effect in the post-treatment plant is a mixer-settler and a pulse extraction column. The concentration of the plutonium solution in the pulse extraction column is one of the key objects of concern, and directly reflects the operating process state of the post-treatment plant.
The indoor radiation dose of the equipment where the pulse extraction column is located is high, and the measurement cannot be carried out on site, so that a measurement signal needs to be led out of the equipment room for monitoring. The method has some defects, such as the number of detectors is small, the change condition of the whole pulse extraction column can not be reflected in time, the detectors are generally fixed at a certain measuring point, the maintenance can not be carried out, the calibration can not be carried out, whether the work is normal or not can not be determined, and the reliability of the measuring result is poor.
SUMMERY OF THE UTILITY MODEL
The shortcoming to original monitoring facilities, the utility model aims at providing a bushing apparatus of on-line monitoring pulse extraction post plutonium concentration, the device can place a plurality of neutron detectors, thereby carry out on-line monitoring to the plutonium solution of the different plate sections of whole pulse extraction post, and under the prerequisite that does not get into the equipment room, can realize the change and the scale to neutron detector, consequently, can be accurate reflect the change condition of plutonium solution concentration in the pulse extraction post, thereby provide a conventional technology and critical safety monitoring technical means for the aftertreatment factory.
For reaching above purpose, the utility model discloses a technical scheme be a sleeve pipe device that is used for pulse extraction post plutonium concentration of on-line monitoring aftertreatment factory for place series detection device, series detection device passes through the cable series by a plurality of neutron detector and constitutes, wherein, include return bend and the straight tube of connecting through the reducing head, series detection device can pass through the return bend business turn over the straight tube.
Furthermore, the return bend comprises three sections of pipe series connection, and every section the radian of pipe is 90 degrees, and the three sections the pipe is in a plane, becomes S molding, prevents that the radiation from passing through.
Further, the diameter of the bent pipe is larger than that of the straight pipe.
Furthermore, the inner diameter of the elbow is 90-100mm, and the thickness of the pipe wall is 4-5 mm.
Further, the inner diameter of the straight pipe is 55mm, and the wall thickness of the pipe is 5 mm.
Furthermore, the elbow pipe, the straight pipe and the reducing head are all made of stainless steel materials and are connected together through welding.
The beneficial effects of the utility model reside in that:
1. the utility model provides a bushing apparatus needs the pre-installation to be close to the indoor position of pulse extraction post 1 of after-treatment factory equipment, just can measure the plutonium solution of each board section of pulse extraction post 1 through placing neutron detector 7 in straight tube 3, thereby in time reflect the situation of change of solution concentration, the purpose of on-line monitoring has been reached, when solution concentration takes place unusually, can in time discover and adjust, thereby prevent the occurence of failure, there is very important effect to the technology operation, also can regard as an important technological means of critical safety monitoring simultaneously.
2. The replacement and maintenance of the neutron detector 7 can be realized without the need of entering an equipment room by workers, and the radiation danger of the workers is reduced.
Drawings
Fig. 1 is a schematic diagram of a casing device for online monitoring of plutonium concentration in a pulse extraction column of an aftertreatment plant according to an embodiment of the present invention, which is disposed on the pulse extraction column 1;
FIG. 2 is a schematic diagram of a casing device for on-line monitoring of plutonium concentration in a pulse extraction column of an aftertreatment plant according to an embodiment of the present invention;
fig. 3 is a schematic view of the elbow pipe 2 according to the embodiment of the present invention disposed in the wall 5 of the equipment room;
fig. 4 is a schematic view of a neutron detector 7 disposed in the straight pipe 3 according to the embodiment of the present invention;
in the figure: 1-pulse extraction column, 2-bent pipe, 3-straight pipe, 4-neutron moderating body, 5-wall body, 6-reducing head, 7-neutron detector and 8-cable.
Detailed Description
The invention is further described with reference to the following figures and examples.
As shown in FIG. 1, the utility model provides a pair of a bushing apparatus for on-line monitoring aftertreatment plant pulse extraction post plutonium concentration for place series detection device, measure the plutonium concentration in the indoor pulse extraction post 1 of equipment. The series detection device is formed by connecting a plurality of neutron detectors 7 in series through a cable 8. As shown in FIG. 2, the utility model provides a pair of a bushing apparatus for pulse extraction post plutonium concentration of on-line monitoring aftertreatment plant includes return bend 2 and straight tube 3 connected through reducing head 6, and series detection device can pass through return bend 2 business turn over straight tube 3.
As shown in fig. 3, the bent pipe 2 is pre-embedded in the wall 5 of the equipment room (the thickness of the wall 5 is 1200mm), the bent pipe 2 is formed by connecting three sections of circular pipes in series, the radian of each section of circular pipe is 90 degrees, and the three sections of circular pipes are positioned in one plane; because the dosage in the equipment room where the pulse extraction column 1 is located is high, and the bent pipe 2 is in an S shape, the neutron detector can conveniently pass through (the size of the ordinary neutron detector is phi 25.4 multiplied by 200mm, and the diameter of an outer protective sleeve of the neutron detector is about 45mm), and radiation can be effectively prevented from passing through.
The diameter of the bent pipe 2 is larger than that of the straight pipe 3.
The inner diameter of the elbow pipe 2 is 90-100mm, and the thickness of the pipe wall is 4-5 mm.
The inner diameter of the straight tube 3 was 55mm, and the wall thickness was 5 mm.
The bent pipe 2, the straight pipe 3 and the reducing head 6 are all made of stainless steel materials and are connected together through welding.
The practical application of the casing device for monitoring the plutonium concentration of the pulse extraction column in the post-treatment plant on line is illustrated;
the height of pulse extraction post 1 is about 12.3 meters, the plate section part height of pulse extraction post 1 is about 8 meters, design plate section part is every 1 meter place a neutron detector 7, then 9 neutron detectors 7 are needed altogether, 9 neutron detectors 7 are connected together in series, connect by cable 8, through receiving and releasing cable 8, make neutron detector 7 arrive appointed measuring position in the straight tube 3, just can measure the plutonium solution in each plate section in the pulse extraction post 1, and when neutron detector 7 broke down or need carry out the scale, just can pull cable 8, take out neutron detector 7, carry out corresponding operation, thereby the staff need not to enter into equipment room the inside.
As shown in fig. 4, in order to improve the measurement efficiency, a neutron moderator 4 needs to be placed outside the straight tube 3 at the position of each neutron detector 7, wherein the moderating is used for moderating fast neutrons into thermal neutrons, so as to improve the neutron detection efficiency of the neutron detector 7, and the neutron moderator 4 is used for shielding the plutonium solution in other plate sections of the pulse extraction column 1 and neutrons scattered in the environment, so as to achieve the purpose of measuring the neutrons emitted by the plutonium solution in the corresponding plate section.
The device of the present invention is not limited to the specific embodiments described in the embodiments, and those skilled in the art can obtain other embodiments according to the technical solution of the present invention, which also belongs to the technical innovation scope of the present invention.
Claims (6)
1. The utility model provides a bushing apparatus for on-line monitoring post treatment plant pulse extraction post plutonium concentration for place series detection device, series detection device is established ties through cable (8) by a plurality of neutron detector (7) and is constituteed characterized by: the device comprises an elbow (2) and a straight pipe (3) which are connected through a reducer head (6), wherein the series detection device can pass through the elbow (2) to enter and exit the straight pipe (3).
2. The cannula device of claim 1, wherein: the bent pipe (2) is formed by connecting three sections of circular pipes in series, the radian of each section of circular pipe is 90 degrees, and the three sections of circular pipes are positioned in one plane to form an S shape and prevent radiation from passing through.
3. The cannula device of claim 1, wherein: the diameter of the bent pipe (2) is larger than that of the straight pipe (3).
4. The cannula device of claim 1, wherein: the inner diameter of the elbow (2) is 90-100mm, and the thickness of the pipe wall is 4-5 mm.
5. The cannula device of claim 1, wherein: the inner diameter of the straight pipe (3) is 55mm, and the wall thickness of the pipe is 5 mm.
6. The cannula device of claim 1, wherein: the bent pipe (2), the straight pipe (3) and the reducing head (6) are all made of stainless steel materials and are connected together through welding.
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CN202021750634.6U CN213545930U (en) | 2020-08-20 | 2020-08-20 | A bushing apparatus for on-line monitoring post-treatment plant pulse extraction post plutonium concentration |
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CN202021750634.6U CN213545930U (en) | 2020-08-20 | 2020-08-20 | A bushing apparatus for on-line monitoring post-treatment plant pulse extraction post plutonium concentration |
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