CN110828008A - Parameter monitoring and sampling system of nuclear fuel irradiation examination device - Google Patents
Parameter monitoring and sampling system of nuclear fuel irradiation examination device Download PDFInfo
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- CN110828008A CN110828008A CN201911141665.3A CN201911141665A CN110828008A CN 110828008 A CN110828008 A CN 110828008A CN 201911141665 A CN201911141665 A CN 201911141665A CN 110828008 A CN110828008 A CN 110828008A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
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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
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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
- G21C17/112—Measuring temperature
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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
Abstract
The invention discloses a parameter monitoring and sampling system of a nuclear fuel irradiation examination device, which belongs to the technical field of research on reactor fuel irradiation, and comprises a positioning flange and a water inlet pipe assembly, wherein the water inlet pipe assembly is arranged in a positioning groove at the lower end of the positioning flange and welded, a supporting pipe is welded in an annular clamping groove at the lower end of the positioning flange and forms an annular space with the water inlet pipe assembly, a supporting ring is connected at the lower end of the supporting pipe, the water inlet pipe assembly penetrates through the supporting ring and forms clearance fit, and the lower end of the water inlet pipe assembly is sequentially coaxially connected with an orifice plate and; the upper end of the measuring pipe is connected with the quick connector, the other end of the measuring pipe penetrates through the positioning flange and then penetrates through the supporting pipe to form an annular space with the water inlet pipe assembly to be connected with a side hole on the pore plate. The invention aims to solve the technical problems of directly obtaining flow and temperature parameters of a fuel irradiation device in the test process and sampling detection outside a research pile.
Description
Technical Field
The invention relates to the technical field of research on reactor fuel irradiation, in particular to a parameter monitoring and sampling system of a nuclear fuel irradiation examination device.
Background
Various nuclear fuel irradiation tests in China need to be carried out, and requirements for accurately simulating and controlling irradiation test parameters are provided for truly reflecting fuel behaviors of future actual operating environments. The fuel irradiation device is used as a main bearing device for researching nuclear fuel, and the structural characteristics and the performance of the fuel irradiation device are very important to test results. In addition, when the in-pile test is carried out, in order to directly measure the performance change of the test assembly and quickly obtain main parameters in the irradiation test process, the fuel irradiation device is required to be capable of obtaining information such as temperature, flow and loop water quality on line.
At present, both a material irradiation device and a fuel irradiation device are of nonstandard design, and a specific irradiation device needs to be designed according to different irradiation test requirements. Therefore, the measurement and control system attached to the irradiation device is designed specifically. The fuel irradiation device works in a pressure-bearing environment, has high requirements on the sealing performance and the safety of the fuel irradiation device and the pile top, and not only needs to meet the requirement of acquiring irradiation parameters on line under normal working conditions, but also needs to meet the requirement of ensuring the safety in the pile under special working conditions.
In a fuel irradiation test, the temperature, the flow of an inlet and an outlet of an irradiation test section and a cooling water sample need to be monitored on line. Therefore, a parameter monitoring and sampling system is additionally designed on the device section of the fuel irradiation device according to the requirements. The requirements of online monitoring of relevant parameters are met.
Disclosure of Invention
The invention aims to solve the technical problems of directly obtaining flow and temperature parameters of a fuel irradiation device in the test process and sampling detection outside a research pile. Therefore, a system which can meet the requirements of acquiring and detecting data outside the reactor is designed for the fuel irradiation device, and the smooth implementation of the fuel irradiation test is guaranteed.
In order to achieve the above object, the present application provides a parameter monitoring and sampling system for a nuclear fuel irradiation testing device, comprising: the device comprises a positioning flange, a supporting pipe, a water inlet pipe assembly, a supporting ring, a sampling pipe, a pore plate, an inclined hole sleeve, a measuring pipe, a quick connector, an end assembly A, an end assembly B, a steel wire sealing assembly, a protecting pipe and an inclined hole sleeve; the water inlet pipe assembly is installed in a positioning groove at the lower end of the positioning flange and welded, the supporting pipe is welded into an annular clamping groove at the lower end of the positioning flange and forms an annular space with the water inlet pipe assembly, the supporting ring is connected to the lower end of the supporting pipe, the water inlet pipe assembly penetrates through the supporting ring and forms clearance fit, and the lower end of the water inlet pipe assembly is sequentially connected with the pore plate and the sleeve in a coaxial mode; the upper end of the measuring pipe is connected with the quick connector, the other end of the measuring pipe penetrates through the positioning flange, and then penetrates through the supporting pipe and the water inlet pipe assembly to form an annular space which is connected with a side hole on the pore plate; the upper ends of the two protection tubes are respectively connected with the end head assembly A and the end head assembly B, and the other ends of the two protection tubes penetrate through the positioning flange, then penetrate through an annular space formed by the support tube and the water inlet tube assembly, and finally penetrate through inclined holes in the inclined hole sleeve to extend into the irradiation examination section; the sampling tube penetrates through the positioning flange, then penetrates through an annular space formed by the supporting tube and the water inlet tube assembly, and finally penetrates through an inclined hole in the inclined hole sleeve to extend into the irradiation examination section; the steel wire sealing assembly is welded to the positioning flange through a bent pipe.
Preferably, a partition board is arranged inside the pore plate, a circular hole is formed in the partition board, two side holes in the same direction are formed in the side walls on the two sides of the partition board, the two side holes are respectively welded with the two measuring tubes, and the outlets of the measuring tubes are connected with a flow monitoring system through quick connectors to convert pressure signals into flow information.
Preferably, the two protection pipes are bent at the inclined hole sleeve and penetrate through the inclined hole sleeve, and the outlets of the protection pipes are arranged at the inner wall of the sleeve and do not extend out of the sleeve; the other end of the protection tube of the connecting end component B is connected with the plug component. The temperatures at the inlet and outlet of the irradiation test section are monitored primarily in the fuel irradiation plant. And a thermocouple for monitoring the outlet temperature of the test section firstly penetrates out of the protection tube, then penetrates through the clamping block of the test section, and is finally welded on the plug assembly arranged at the lower end head of the test section.
Preferably, the protection tubes are mainly used for protecting thermocouples in the temperature monitoring device, and two thermocouples are installed in each protection tube; and a thermocouple penetrates through the protection tube, the end assembly A and the end assembly B, and finally penetrates out of a small hole in the end cover. The end head component A and the end head component B mainly play a role in auxiliary sealing.
Preferably, the sampling tube is bent at the inclined hole sleeve and penetrates through the inclined hole sleeve to extend into the bottom of the test section of the fuel irradiation device along the central axis of the inclined hole sleeve. The sampling tubes at the inlet and outlet of the irradiation test section are monitored primarily in the fuel irradiation plant. The sampling tube is mainly used for monitoring a water sample at an outlet of the irradiation test section, and the water sample at the inlet of the irradiation test section is mainly monitored by the protection tube connected with the end component A.
Preferably, the wire seal assembly comprises: the sealing ring is coaxially stacked in the pipe joint and is compressed by the gland, and the nut is matched with the pipe joint to apply pretightening force to the gland. The fuel irradiation device mainly comprises a device section and an irradiation test section, the parameter monitoring and sampling system is attached to the device section, when the fuel irradiation device is piled, a sleeve of the irradiation device section is inserted into the irradiation test section and connected with a steel wire rope, and the steel wire rope penetrates through the device section and penetrates out of the steel wire sealing assembly.
Preferably, the head assembly a comprises: the end cover is installed in a groove of the conical pipe and welded, an axial outlet of the T-shaped pipe is welded to the bottom of the conical pipe, and a transverse outlet of the T-shaped pipe is connected with the sampling device. The end assembly A is used as a connecting port of the sampling device while sealing the hole on the flange of the leading-out protection pipe.
Preferably, the head assembly B comprises: the end cover B, the conical tube B and the short tube, wherein one end of the short tube is welded to the bottom of the conical tube, and the other end of the short tube is welded to the protection tube. The centers of the nut, the pipe joint, the gland and the sealing ring are all provided with holes which are in clearance fit with the steel wire. And the end component A is connected with a protection pipe and also serves as a sampling pipe at an inlet of the irradiation test section.
One or more technical solutions provided by the present application have at least the following technical effects or advantages:
the invention aims to solve the technical problems of directly obtaining flow and temperature parameters of a fuel irradiation device in the test process and sampling detection outside a research pile. Therefore, a system which can meet the requirements of acquiring and detecting data outside the reactor is designed for the fuel irradiation device, and the smooth implementation of the fuel irradiation test is guaranteed.
In the actual use process, the invention has the following beneficial effects:
1) the invention is internally provided with the pore plate, the thermocouple and the pressure guiding pipe, and after the pore plate, the thermocouple and the pressure guiding pipe are connected with an instrument outside the reactor, the on-line monitoring of irradiation examination parameters such as coolant flow, temperature, examination section pressure difference, test assembly temperature and the like is realized during the nuclear fuel irradiation examination period, and the invention has an instrumented function.
2) The invention adopts the connection of the flange and the top cover of the pressure shell, the good sealing between the flange and the measuring tube, between the flange and the connecting rod, and between the measuring tube and the thermocouple, and can ensure the tightness and the integrity of the pressure boundary of a loop when being applied to a research test pile of the pressure shell type.
3) The water quality sampling tube is arranged at the outlet of the examination section, so that the water quality change condition of the coolant flowing through the examination section can be monitored at any time, a tester can judge the nuclear fuel irradiation examination condition, and the safety monitoring requirement of the in-pile test is met.
4) The acquisition of monitoring parameters and the sampling of the primary loop water are completed in the main control room and the sampling room, and are far away from a pile hall, so that the risk of radiation to workers is avoided.
5) According to the invention, two thermocouples can be arranged at the same measuring point, the data acquisition and accuracy are guaranteed, and the sealing performance is guaranteed by adopting an independent sealing mode at the position where the thermocouples are led out of the pile top.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiments of the invention and together with the description serve to explain the principles of the invention;
FIG. 1 is a schematic diagram of the general structure of the present invention;
FIG. 2 is a schematic diagram of the general structure of the present invention;
FIG. 3 is a schematic end view of the present invention;
FIG. 4 is a schematic view of a wire seal assembly of the present invention;
FIG. 5 is a schematic view of head assembly A of the present invention;
FIG. 6 is a schematic view of a head assembly B of the present invention;
FIG. 7 is a schematic view of a plug assembly of the present invention;
FIG. 8 is a schematic view of a water intake riser assembly of the present invention;
FIG. 9 is a schematic view of an orifice plate configuration of the present invention;
FIG. 10 is a schematic view of the slant hole sleeve structure of the present invention;
the device comprises a positioning flange 1, a support pipe 2, a water inlet pipe assembly 3, a support ring 4, a sampling pipe 5, a pore plate 6, a plug assembly 7, a sleeve 8, a measuring pipe 9, a quick joint 10, a head assembly A11, a head assembly 12, a head assembly B13, a steel wire sealing assembly 14a, a first protection pipe 14B, a second protection pipe 15, an inclined hole sleeve 111a, an end cover A112a, a conical pipe A, an end cover B111B, a conical pipe B, a T-shaped pipe 113, a short pipe 121, a nut 131, a pipe joint 132, a gland 133, a gland 134 and a sealing ring.
Detailed Description
In order that the above objects, features and advantages of the present invention can be more clearly understood, a more particular description of the invention will be rendered by reference to the appended drawings. It should be noted that the embodiments and features of the embodiments of the present application may be combined with each other without conflicting with each other.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention, however, the present invention may be practiced in other ways than those specifically described and thus the scope of the present invention is not limited by the specific embodiments disclosed below.
As shown in fig. 1-10, the embodiment of the present application provides a nuclear fuel irradiation examination device parameter monitoring and sampling system, which includes a positioning flange 1, a support pipe 2, a water inlet pipe assembly 3, a support ring 4, a sampling pipe 5, a pore plate 6, an inclined hole casing pipe 7, a casing pipe 8, a measurement pipe 9, a quick connector 10, a tip assembly a11, a tip assembly B12, a steel wire sealing assembly 13, a first protection pipe 14a, a second protection pipe 14B and an inclined hole casing pipe 15, wherein the support pipe 2 is welded in an annular clamping groove at the lower end of the positioning flange 1 and forms an annular space with the water inlet pipe assembly 3, the support ring 4 is connected to the lower end of the support pipe 2, the water inlet pipe assembly 3 passes through the support ring 4 and forms a clearance fit, and the lower end of the water inlet pipe assembly 3 is sequentially coaxially connected; the upper end of the measuring pipe 9 is connected with a quick connector 10, the other end of the measuring pipe passes through the positioning flange 1, and then passes through the supporting pipe 2 and the water inlet pipe assembly 3 to form an annular space which is connected with a side hole on the pore plate 6; the upper ends of the first protection pipe 14a and the second protection pipe 14B are respectively connected with a terminal assembly A11 and a terminal assembly B12, the other ends of the first protection pipe and the second protection pipe penetrate through the positioning flange 1, then penetrate through an annular space formed by the support pipe 2 and the water inlet pipe assembly 3, and finally penetrate through an inclined hole in the inclined hole sleeve 7 to extend into an irradiation examination section; the sampling tube 5 penetrates through the positioning flange 1, then penetrates through an annular space formed by the supporting tube 2 and the water inlet tube component 3, and finally penetrates through an inclined hole in an inclined hole sleeve 7 to extend into an irradiation examination section; the steel wire sealing assembly 13 is welded to the positioning flange 1 through a bent pipe.
In the embodiment of the present application, a partition board is disposed inside the orifice plate 6, a circular hole is formed in the partition board, two side holes in the same direction are formed in the side walls of the two sides of the partition board, and the two side holes are respectively welded to the two measuring tubes 9.
In the embodiment of the present application, the first protection tube 14a and the second protection tube 14b are bent at the inclined hole casing 15 and pass through the inclined hole casing 15, and the outlet of the first protection tube 14a is disposed at the inner wall of the casing 8 and does not extend out of the casing 8; the other end of the second protective tube 14B connected to the end assembly B12 is connected to the plug assembly 7.
In the embodiment of the present application, the sampling tube 5 is bent at the inclined-hole casing 15 and penetrates through the inclined-hole casing 15, and extends into the bottom of the test section of the fuel irradiation device along the central axis of the inclined-hole casing 15.
In the embodiment of the present application, the above-mentioned wire sealing assembly 13 includes: the pipe joint comprises a nut 131, a pipe joint 132, a gland 133 and a sealing ring 134, wherein the sealing ring 134 is coaxially stacked in the pipe joint 132 and is pressed by the gland 133, and the nut 131 is matched with the pipe joint 132 to apply pre-tightening force to the gland 133.
In the embodiment of the present application, the head assembly a11 includes: an end cover A111a, a tapered pipe A112a and a T-shaped pipe 113, wherein the end cover A111a is arranged in a groove of the tapered pipe A112a and welded, an axial outlet of the T-shaped pipe 113 is welded to the bottom of the tapered pipe A112a, and a transverse outlet of the T-shaped pipe 113 is connected with a sampling device.
In the embodiment of the present application, the terminal assembly B12 includes an end cap B111B, a tapered tube B112B, and a short tube 121, wherein one end of the short tube 121 is welded to the bottom of the tapered tube B112B, and the other end is welded to the second protection tube 14B.
In the embodiment of the present application, the nut 131, the pipe joint 132, the gland 133, and the seal ring 134 are provided with holes at their centers for fitting the steel wires with gaps.
In the embodiment of the present application, the above-mentioned protective tube connected to the end assembly a11 also serves as a sampling tube at the inlet of the irradiation test section.
Example 1:
the fuel irradiation device comprises a device section and an irradiation test section, and the parameter monitoring and sampling system is attached to the device section and mainly used for monitoring parameter information of the irradiation test section and taking a loop water sample.
The system depends on the device section of the fuel irradiation device, and when the device section is connected with the irradiation test section, the sleeve 8 is inserted into the outer sleeve of the irradiation test section and is connected with the outer sleeve by combining a steel wire rope. The whole fuel irradiation device is inserted into the reactor from the top of the reactor and is connected with the pressure shell by a flange, so that the pressure relief in the reactor is avoided. Wherein, the measuring tube 9, the quick connector 10 and the orifice plate 6 are combined, and mainly monitor the flow of cooling water entering the fuel irradiation device; the end assembly A11, the end assembly B12 and the protection tubes are combined to mainly protect the thermocouple, so that the thermocouple is prevented from being damaged in the process of leading out from the stack, and one protection tube is also used as a sampling device member at the inlet of the irradiation test section; the sampling tube 5 mainly obtains a water sample at the outlet of the irradiation test section. In summary, the invention monitors temperature and flow and completes sampling task on line outside the reactor.
While preferred embodiments of the present invention have been described, additional variations and modifications in those embodiments may occur to those skilled in the art once they learn of the basic inventive concepts. Therefore, it is intended that the appended claims be interpreted as including preferred embodiments and all such alterations and modifications as fall within the scope of the invention.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include such modifications and variations.
Claims (10)
1. A nuclear fuel irradiation testing device parameter monitoring and sampling system, characterized in that, the system includes:
the device comprises a positioning flange (1), a supporting pipe (2), a water inlet pipe assembly (3), a supporting ring (4), a sampling pipe (5), a pore plate (6), an inclined hole sleeve (7), a sleeve (8), a measuring pipe (9), a quick connector (10), an end assembly A (11), an end assembly B (12), a steel wire sealing assembly (13), a first protection pipe (14a), a second protection pipe (14B) and an inclined hole sleeve (15); the water inlet pipe assembly (3) is arranged in a positioning groove at the lower end of the positioning flange (1), the supporting pipe (2) is fixed in an annular clamping groove at the lower end of the positioning flange (1) and forms an annular space with the water inlet pipe assembly (3), the supporting ring (4) is connected to the lower end of the supporting pipe (2), the water inlet pipe assembly (3) penetrates through the supporting ring (4) and forms clearance fit, and the lower end of the water inlet pipe assembly (3) is sequentially coaxially connected with the pore plate (6) and the sleeve (8); one end of the measuring pipe (9) is connected with a quick connector (10), and the other end of the measuring pipe (9) sequentially penetrates through the positioning flange (1) and the annular space and then is connected with a side hole on the pore plate (6); one end of each of the first protection pipe (14a) and the second protection pipe (14B) is connected with the end head assembly A (11) and the end head assembly B (12) respectively, and the other end of each of the first protection pipe (14a) and the second protection pipe (14B) sequentially penetrates through the positioning flange (1), the annular space and the inclined hole in the inclined hole sleeve (7) and extends into the irradiation examination section; one end of the sampling tube (5) sequentially penetrates through the positioning flange (1), the annular space and the inclined hole in the inclined hole sleeve (7) and extends into the irradiation examination section; the steel wire sealing component (13) is fixedly connected with the positioning flange (1).
2. The nuclear fuel irradiation testing device parameter monitoring and sampling system according to claim 1, wherein a baffle plate is arranged inside the orifice plate (6), a circular hole is formed on the baffle plate, two side holes in the same direction are formed on the side walls at two sides of the baffle plate, and the two side holes are respectively welded with the two measuring tubes (9).
3. The nuclear fuel irradiation testing device parameter monitoring and sampling system according to claim 1, wherein the first protection tube (14a) and the second protection tube (14b) are bent at the inclined hole casing (15) and penetrate through the inclined hole casing (15), and the outlets of the first protection tube (14a) are arranged at the inner wall of the casing (8) and do not extend out of the casing (8); the other end of the second protection pipe (14B) connected with the end component B (12) is connected with the end cap component (7).
4. The nuclear fuel irradiation testing device parameter monitoring and sampling system according to claim 3, wherein the first protection pipe (14a) and the second protection pipe (14b) connected with the end assembly A (11) are used as sampling pipes at the inlet of the irradiation test section.
5. The parameter monitoring and sampling system of the nuclear fuel irradiation testing device according to claim 1, wherein the sampling tube (5) is bent at the inclined-hole casing (15) and penetrates through the inclined-hole casing (15) to extend into the bottom of the testing section of the fuel irradiation device along the central axis of the inclined-hole casing (15).
6. The nuclear fuel irradiation testing device parameter monitoring and sampling system of claim 1, wherein the wire seal assembly (13) comprises: the sealing ring sealing device comprises a nut (131), a pipe joint (132), a gland (133) and a sealing ring (134), wherein the sealing ring (134) is coaxially stacked in the pipe joint (132) and is compressed by the gland (133), and the nut (131) is matched with the pipe joint (132) to apply pretightening force to the gland (133).
7. The nuclear fuel irradiation testing device parameter monitoring and sampling system according to claim 6, wherein the nut (131), the pipe connector (132), the gland (133) and the sealing ring (134) are provided with holes in the centers thereof, which are in clearance fit with the steel wires.
8. The nuclear fuel irradiation testing device parameter monitoring and sampling system of claim 1, wherein the head assembly a (11) comprises: the device comprises an end cover A (111a), a conical pipe A (112a) and a T-shaped pipe (113), wherein the end cover A (111a) is installed in a groove of the conical pipe A (112a) and welded, an axial outlet of the T-shaped pipe (113) is welded to the bottom of the conical pipe A (112a), and a transverse outlet of the T-shaped pipe (113) is connected with a sampling device.
9. The nuclear fuel irradiation testing device parameter monitoring and sampling system of claim 1, wherein the head assembly B (12) comprises: the end cover B (111B), the conical tube B (112B) and the short tube (121), one end of the short tube (121) is welded to the bottom of the conical tube B (112B), and the other end of the short tube is welded to the second protection tube (14B).
10. The nuclear fuel irradiation testing device parameter monitoring and sampling system according to claim 1, wherein the steel wire sealing assembly (13) is welded to the positioning flange (1) through a bent pipe.
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| CN201911141665.3A CN110828008B (en) | 2019-11-20 | 2019-11-20 | Parameter monitoring and sampling system of nuclear fuel irradiation examination device |
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| CN111397970A (en) * | 2020-04-29 | 2020-07-10 | 中国核动力研究设计院 | Liquid metal sampler and liquid metal sampling method |
| CN112366021A (en) * | 2020-11-09 | 2021-02-12 | 中国工程物理研究院核物理与化学研究所 | Equipment and method for realizing homogenization of reactor irradiation parameters |
| CN112763279A (en) * | 2020-12-21 | 2021-05-07 | 苏州原核仪表成套有限公司 | Sampling head structure, air pipe structure, sampling head and air pipe type selection method |
| CN113724903A (en) * | 2021-08-27 | 2021-11-30 | 中国核动力研究设计院 | Sensor examination device |
| CN115985546A (en) * | 2022-11-07 | 2023-04-18 | 中国核动力研究设计院 | Half-and-half type partitioned temperature control irradiation device |
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| CN112366021A (en) * | 2020-11-09 | 2021-02-12 | 中国工程物理研究院核物理与化学研究所 | Equipment and method for realizing homogenization of reactor irradiation parameters |
| CN112366021B (en) * | 2020-11-09 | 2022-09-23 | 中国工程物理研究院核物理与化学研究所 | Equipment and method for realizing homogenization of reactor irradiation parameters |
| CN112763279A (en) * | 2020-12-21 | 2021-05-07 | 苏州原核仪表成套有限公司 | Sampling head structure, air pipe structure, sampling head and air pipe type selection method |
| CN113724903A (en) * | 2021-08-27 | 2021-11-30 | 中国核动力研究设计院 | Sensor examination device |
| CN113724903B (en) * | 2021-08-27 | 2023-11-24 | 中国核动力研究设计院 | Sensor examination device |
| CN115985546A (en) * | 2022-11-07 | 2023-04-18 | 中国核动力研究设计院 | Half-and-half type partitioned temperature control irradiation device |
| CN115985546B (en) * | 2022-11-07 | 2024-03-19 | 中国核动力研究设计院 | Half-and-half type partition temperature control irradiation device |
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