CN112130194A - A neutron detector rapid inspection device - Google Patents
A neutron detector rapid inspection device Download PDFInfo
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- CN112130194A CN112130194A CN202010843590.XA CN202010843590A CN112130194A CN 112130194 A CN112130194 A CN 112130194A CN 202010843590 A CN202010843590 A CN 202010843590A CN 112130194 A CN112130194 A CN 112130194A
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- 238000007689 inspection Methods 0.000 title claims abstract description 26
- 238000001514 detection method Methods 0.000 claims abstract description 33
- 238000007789 sealing Methods 0.000 claims description 7
- 239000004698 Polyethylene Substances 0.000 claims description 6
- -1 polyethylene Polymers 0.000 claims description 6
- 229920000573 polyethylene Polymers 0.000 claims description 6
- 239000000463 material Substances 0.000 claims description 4
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 5
- 238000012360 testing method Methods 0.000 abstract description 4
- 238000012805 post-processing Methods 0.000 abstract 1
- 238000000605 extraction Methods 0.000 description 7
- 229910052778 Plutonium Inorganic materials 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 5
- 238000012958 reprocessing Methods 0.000 description 5
- 229910052770 Uranium Inorganic materials 0.000 description 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 4
- 238000010586 diagram Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000000638 solvent extraction Methods 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
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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
Description
技术领域technical field
本发明属于乏燃料后处理技术领域,具体涉及一种中子探测器快速检验装置。The invention belongs to the technical field of spent fuel reprocessing, and in particular relates to a rapid inspection device for a neutron detector.
背景技术Background technique
乏燃料又称辐照核燃料,是经受过辐射照射、使用过的核燃料,通常是由核电站的核反应堆产生。把已经使用的3%-4%的铀废料(乏燃料),以化学方法将铀和钚从裂变产物中分离出来,称为乏燃料再溶解和后处理技术。回收的铀和钚可在核电厂混合氧化物燃料中再循环使用,以生产更多能量,从而使铀资源得到更充分利用并减少浓缩需求。后处理也通过减少高放废物的体积和去除钚有助于废物的最终处置。Spent fuel, also known as irradiated nuclear fuel, is nuclear fuel that has been exposed to radiation and used, usually produced by the nuclear reactor of a nuclear power plant. The 3%-4% uranium waste (spent fuel) that has been used is chemically separated from uranium and plutonium from fission products, which is called spent fuel redissolving and reprocessing technology. Recovered uranium and plutonium can be recycled in mixed oxide fuel in nuclear power plants to produce more energy, thereby making uranium resources more efficient and reducing enrichment needs. Reprocessing also aids in the final disposal of waste by reducing the volume of high-level radioactive waste and removing plutonium.
在后处理工厂中普遍使用的效果良好的溶剂萃取设备有混合澄清槽和脉冲萃取柱。脉冲萃取柱中钚溶液的浓度是关注的重点对象之一,直接反应了后处理厂的运行工艺状态。如图1所示,目前对脉冲萃取柱中钚溶液浓度的监测方法主要是在设备室内靠近脉冲萃取柱放置一个串联探测装置进行测量,串联探测装置由若干个中子探测器串联组成,放置在一个套管内,串联探测装置可以从套管内进出。该串联探测装置中的中子探测器需要定期进行检验,如何方便、快捷的对该串联探测装置进行检验是研究的重点之一。Well-known solvent extraction equipment commonly used in reprocessing plants are mixer-settler tanks and pulsed extraction columns. The concentration of the plutonium solution in the pulse extraction column is one of the key objects of concern, which directly reflects the operating process state of the reprocessing plant. As shown in Figure 1, the current monitoring method for the concentration of plutonium solution in the pulse extraction column is mainly to place a series detection device near the pulse extraction column in the equipment room for measurement. The series detection device is composed of several neutron detectors connected in series and placed in Within a casing, the in-line detection device can be accessed and exited from the casing. The neutron detector in the series detection device needs to be inspected regularly, and how to inspect the series detection device conveniently and quickly is one of the key points of the research.
发明内容SUMMARY OF THE INVENTION
本发明的目的是提供一种检测装置,能够对串联探测装置中的每个中子探测器进行快速的检验,从而使中子中子探测器的测量结果更加准确。The purpose of the present invention is to provide a detection device that can quickly test each neutron detector in the series detection device, so that the measurement results of the neutron neutron detector are more accurate.
为达到以上目的,本发明采用的技术方案是一种中子探测器快速检验装置,用于对串联探测装置中的中子探测器进行测量,所述串联探测装置由若干个所述中子探测器串联组成,其中,包括内部设有中子源的屏蔽容器,所述屏蔽容器上还设有能够通过所述串联探测装置的穿孔。In order to achieve the above purpose, the technical solution adopted in the present invention is a rapid inspection device for neutron detectors, which is used to measure the neutron detectors in the series detection device. It is composed of a series of detectors, which includes a shielding container with a neutron source inside, and the shielding container is also provided with a perforation that can pass through the series detection device.
进一步,所述屏蔽容器内部设有中子源放置孔,所述中子源设置在所述中子源放置孔中。Further, a neutron source placement hole is provided inside the shielding container, and the neutron source is disposed in the neutron source placement hole.
进一步,所述穿孔贯穿所述屏蔽容器。Further, the perforation penetrates the shielding container.
进一步,所述中子源靠近所述穿孔。Further, the neutron source is close to the through hole.
进一步,所述中子源放置孔通过密封塞封堵。Further, the neutron source placement hole is blocked by a sealing plug.
进一步,所述屏蔽容器的材质为聚乙烯,能够慢化所述中子源发出的中子。Further, the material of the shielding container is polyethylene, which can moderate the neutrons emitted by the neutron source.
进一步,所述密封塞的材质为聚乙烯。Further, the material of the sealing plug is polyethylene.
进一步,所述屏蔽容器为圆柱体,所述中子源放置孔位于屏蔽容器的轴线位置,所述穿孔从所述中子源放置孔的密封的底端附近穿过。Further, the shielding container is a cylinder, the neutron source placement hole is located at the axial position of the shielding container, and the perforation passes through the vicinity of the sealed bottom end of the neutron source placement hole.
进一步,所述屏蔽容器上还设有提手。Further, a handle is also provided on the shielding container.
本发明的有益效果在于:The beneficial effects of the present invention are:
1.屏蔽容器4的尺寸约为Φ250mm×250mm,重量大约为12kg,便于携带。1. The size of the
2.无需拆卸串联探测装置就实现了对串联探测装置中的每个中子探测器10进行快速的检验。2. The rapid inspection of each
3.检验操作简单、方便。3. The inspection operation is simple and convenient.
附图说明Description of drawings
图1是本发明背景技术部分所述的设置在设备室内的脉冲萃取柱1上的套管2的示意图,由若干个中子探测器10串联组成的串联探测装置设置在套管2内;Fig. 1 is the schematic diagram of the
图2是本发明具体实施方式中所述的一种中子探测器快速检验装置的立体示意图;2 is a schematic perspective view of a rapid inspection device for a neutron detector described in the specific embodiments of the present invention;
图3是本发明具体实施方式中所述的一种中子探测器快速检验装置的平面示意图;3 is a schematic plan view of a device for rapid inspection of a neutron detector according to the specific embodiment of the present invention;
图4是图3的A向视图;Fig. 4 is the A-direction view of Fig. 3;
图5是图3的B向视图;Fig. 5 is the B-direction view of Fig. 3;
图6是串联探测装置在本发明具体实施方式中所述的一种中子探测器快速检验装置中的检测过程的示意图;6 is a schematic diagram of a detection process of a series detection device in a neutron detector rapid inspection device described in the specific embodiments of the present invention;
图中:1-脉冲萃取柱,2-套管,3-墙体,4-屏蔽容器,5-密封塞,6-穿孔,7-提手,8-中子源放置孔,9-中子源,10-中子探测器。In the picture: 1-pulse extraction column, 2-sleeve, 3-wall, 4-shielding container, 5-sealing plug, 6-perforation, 7-handle, 8-neutron source placement hole, 9-neutron source, 10-neutron detector.
具体实施方式Detailed ways
下面结合附图和实施例对本发明作进一步描述。The present invention will be further described below with reference to the accompanying drawings and embodiments.
如图2至图5所示,本发明提供的一种中子探测器快速检验装置,用于对串联探测装置中的中子探测器10进行测量,串联探测装置由若干个中子探测器10串联组成,本发明提供的一种中子探测器快速检验装置是一个内部设有中子源9的屏蔽容器4,屏蔽容器4能够屏蔽中子源9发出的放射性粒子,屏蔽容器4上还设有能够通过串联探测装置的穿孔6。As shown in FIG. 2 to FIG. 5 , the present invention provides a rapid inspection device for neutron detectors, which is used to measure the
屏蔽容器4内部设有中子源放置孔8,中子源9设置在中子源放置孔8中。A neutron
穿孔6贯穿屏蔽容器4。The
中子源9靠近穿孔6。The
中子源放置孔8通过密封塞5封堵。The neutron
屏蔽容器4的材质为聚乙烯,能够慢化中子源9发出的中子。The material of the
密封塞5为棒状,材质为聚乙烯。The sealing plug 5 is rod-shaped and made of polyethylene.
屏蔽容器4为圆柱体,中子源放置孔8位于屏蔽容器4的轴线位置,穿孔6从中子源放置孔8的密封的底端附近穿过。The
屏蔽容器4上还设有提手7,方便操作人员提着装置到指定位置进行操作。The
举例说明本发明所提供的一种中子探测器快速检验装置的实际应用;An example is given to illustrate the practical application of the device for rapid inspection of a neutron detector provided by the present invention;
如图1所示,脉冲萃取柱1的高度约为12.3米,板段部分高度约为8米,设计板段部分每隔1米放置一个中子探测器10,则共需要9个中子探测器10,中子探测器10组成一个串联探测装置放入到套管2内,串联探测器可以通过人力进出套管2。As shown in Fig. 1, the height of the
对串联探测装置进行检验的过程如图6所示,屏蔽容器4的中子源放置孔8内设置中子源9,串联探测装置上的中子探测器10依次通过穿孔6进行检验,对一个中子探测器10检验完成后,移动串联探测装置,对下一个中子探测器10进行测试,直到所有的中子探测器10检验完成。The process of inspecting the series detection device is shown in FIG. 6 , a
所有的中子探测器10的连接线束均在串联探测装置的一侧引出。在检验时,需要将连接线束连接到对应的电子学器件中进行测试,如果中子探测器10发生故障可以及时更换,检验完成后,将中子源9取出,串联探测装置放入套管2中继续进行工作。All the connection harnesses of the
本发明所述的装置并不限于具体实施方式中所述的实施例,本领域技术人员根据本发明的技术方案得出其他的实施方式,同样属于本发明的技术创新范围。The device described in the present invention is not limited to the embodiments described in the specific embodiments, and those skilled in the art can obtain other embodiments according to the technical solutions of the present invention, which also belong to the technical innovation scope of the present invention.
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CN113885071A (en) * | 2021-09-02 | 2022-01-04 | 中广核工程有限公司 | Method for verifying validity of reactor core subcritical supervision neutron detector |
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