CN106531245B - Used in nuclear power station in-pile instrument sheath assembly - Google Patents
Used in nuclear power station in-pile instrument sheath assembly Download PDFInfo
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- CN106531245B CN106531245B CN201611050199.4A CN201611050199A CN106531245B CN 106531245 B CN106531245 B CN 106531245B CN 201611050199 A CN201611050199 A CN 201611050199A CN 106531245 B CN106531245 B CN 106531245B
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- neutron detector
- thermocouple
- power station
- collector
- nuclear power
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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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
- G21C17/108—Measuring reactor flux
-
- 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
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present invention relates to a kind of used in nuclear power station in-pile instrument sheath assemblies, including armoured thermocouple, collector, neutron detector, an at least armoured thermocouple and branched neutron detector are fixed together by collector soldering, the neutron detector is self-power neutron detector, by emitter, collect body, insulator and cable composition, one neutron detector length of longest corresponds to entire reactor core height in branched neutron detector, remaining neutron detector length is with longest neutron detector length by equidistantly successively decreasing or neutron detector length is identical, it is equally spaced in an axial direction.It is the configuration of the present invention is simple, firm, small, it can preferably adapt to complex environment in heap.The temperature that present invention can be suitably applied to the outlet of nuclear power station reactor core measures and the measurement of reactor core neutron fluence rate, service life are long.
Description
Technical field
The present invention relates to a kind of reactor core nuclear instrument more particularly to a kind of integrated thermal electric idol and self-power neutron detectors
Nuclear instrument, is suitable for the measurement of nuclear power station reactor core outlet temperature and reactor core neutron fluence rate measures.
Background technology
In nuclear power station normal course of operation, reactor core internal high temperature, high pressure, high corrosion and intense radiation.Work as reactor
Power is run in 25% or more of rated power, needs continuously to monitor current reactor using the monitoring system of heap core inner
Safety allowance, and correspondingly control reactivity.Cold degree is owed for post accident monitoring core exit temperature, measurement reactor core is needed to go out
The fluid temperature of mouth.In-pile instrument sheath assembly life requirements is up to 20 years.To reduce the interface of nuclear instrument inside reactor,
It reduces complexity and then improves reliability, thermocouple and self-power neutron detector are integrated in in-pile instrument sheath assembly.
It is mainly used for measuring the axially and radially distribution of reactor core neutron, monitoring core power distortion accumulates burnup
Data are the important measurement means that nuclear plant safety reliably starts, runs.
The major function of SPND for nuclear power station is：
1. the continuous distribution and variation measured and monitor reactor core active region neutron fluence, flattens neutron fluence, to realize work(
The optimal distribution of rate density provides foundation.
2. accumulating the burn-up level data of fuel assembly, guidance is rationally reloaded.
3. participating in reactor protection, that is, PP2 (2 classes are protected in advance, forbid rod withdrawal) is participated in, PP1 (protect in advance, fast prompt drop work(by 1 class
Rate) and EP (breakdown).
4. can be used as one of the foundation for calculating fuel element linear heat generation rate and nucleateboiling ratio DNBR.
Self-powered detector is a kind of to generate output current by nuclear decay after own absorption neutron under actinism
Solid probe.It has simple in structure, small, light-weight, corrosion-resistant, high temperature high voltage resistant, measurement range is wide, it is attached to be not required to
It powers up, the advantages such as strong antijamming capability, operating cost are low
Core temperature measuring system reactor fuel module outlet temperature under nominal situation and accident conditions for monitoring, with
Determine that the abundant degree of Core cooling, the system are one of important monitoring means for ensureing nuclear plant safety operation and accident
A part for monitoring system (PAMS) afterwards, therefore use Redundancy Design
China's nuclear power is greatly developed, and scale constantly expands, growing day by day for the demand of in-pile instrument sheath assembly, and is wanted
It asks and improves the nuclear instrument localization rate of parts and components.In-pile instrument sheath assembly technical difficulty is high, more novel.
The nuclear power station reactor core refulling cycle, reactor was continuously uninterrupted during this period between 12 months to 18 months
Operation causes coolant loss accident, the pollution of nuclear radiation content leaks that can seriously affect nuclear power station such as in-pile instrument casing damage
Operational safety personnel safety within and around.
Invention content
The technical problem to be solved by the present invention is to：A kind of even reactor core with self-power neutron detector of integrated thermal electric is provided
Nuclear instrument, to solve the problems, such as that existing reactor core nuclear instrument interface dispersion, service life are shorter.
In order to solve the above technical problems, the technical solution adopted in the present invention is：A kind of used in nuclear power station in-pile instrument casing
Component, including armoured thermocouple, collector, neutron detector, at least an armoured thermocouple and branched neutron detector pass through collection
Pipe soldering is fixed together, and the neutron detector is self-power neutron detector, by emitter, collects body, insulator and electricity
Cable forms, and one neutron detector length of longest corresponds to entire reactor core height, remaining neutron in branched neutron detector
Detector length with longest neutron detector length by equidistantly successively decreasing or neutron detector length is identical, equidistant in an axial direction point
Cloth.
Described collector one end is welded to connect by collector upper connector and flexible metal conduit, and the collector other end passes through connector
It being welded to connect with shell, flexible metal conduit is welded to connect by connecting tube and rear shell, and rear shell is welded to connect with electrical cnnector,
Dust cover is screwed in rear shell, armoured thermocouple and neutron detector lead are welded to connect with electrical connector terminal, case nose
It is welded to connect with sub warhead end plug, sub warhead end plug welds end socket after shell fills helium.
The used in nuclear power station in-pile instrument sheath assembly has branched armoured thermocouple and an at least level monitoring thermoelectricity
Even, the level monitoring thermocouple is fixed together with armoured thermocouple soldering, and branched thermocouple enters for monitoring fuel assembly
Mouth coolant temperature measuring point, fuel assembly fuel element outlet temperatures at localized regions measuring point, fuel assembly TBC outlet temperatures are surveyed
Temperature point under point and reactor lid；The level monitoring thermocouple is by electrified heating device TPIU and without electric heater
Thermocouple TP be composed, for the variation of refrigerant level in monitoring pressure container, the various change for providing coolant becomes
The information of gesture and the refrigerant level data under accident conditions.
A background signal line and a corresponding signal wire is arranged in the neutron detector, certainly for offseting signal line
The noise signal of body improves detector sensitivity.
The invention has the advantages that：
1, since neutron detector is self-powered detector, applying bias power supply is not needed, it is only necessary to which picoammeter can be read
Detector current.
2, self-power neutron detector uses low burn consumption material, greatly improves service life, the transmitting of self-powered detector
The sensitive materials such as vanadium, rhodium, cobalt can be used using the big metal material in thermal-neutron reaction section in body.
3, casing and the smaller high temperature for being resistant to heap core inner of sub warhead end plug outer diameter, high pressure, high corrosion and intense radiation, collection
Soldered seam, thermocouple and the neutron detector of weld seam, collector and thermocouple and neutron detector between pipe and casing ensure
It is still resistant to high temperature inside reactor core, high pressure, high corrosion after shell breakage, plays the role of second protection.
4, thermocouple and neutron detector are electrically connected with electrical cnnector, reduce environmental radiation to detector electric loop
Electromagnetic interference improves the accuracy and reliability that temperature measures and neutron fluence rate measures.
5, thermocouple is close to internal surface of sleeve pipe, accelerates thermal response time.
6, in-pile instrument take over penetration piece path is not flat construction, is space curve, therefore cannula tip uses bullet
Header structure plays guide function, and casing is made to facilitate penetration of in-pile instrument take over penetration piece.
7, self-power neutron detector signal wire uses inorganic armored cable, is resistant to reactor core internal high temperature and high irradiation,
In order to avoid self-power neutron detector fails because signal wire damages.
8, insulation uses high-purity alpha-alumina, is not easy the moisture absorption, non-aging, and high-temperature insulation resistance is high, and shadow is penetrated to neutron
It rings less, the measurement accuracy of self-power neutron detector can be effectively improved, itself service life is far beyond self-power neutron detector
Service life, so the service life to detector have no adverse effect.
9, air is first extracted in in-pile instrument component into vacuum, the helium of at least one atmospheric pressure is re-filled with, to avoid ingredient
Complicated air participates in nuclear reaction and then generates interference to measuring, and improves the stability of sheath assembly, and helium thermal conductivity height passes
It is hot fast, also it is the inert gas of a kind of low-density and safety and stability.
10, level monitoring thermocouple is formed by the thermocouple with heater and without the thermocouple of heater, using temperature
The variation of refrigerant level in switch monitors pressure vessel, it is possible to provide the information of the various change trend of coolant can especially carry
For the refrigerant level data under accident conditions.
11, corresponding with signal wire, a background signal line can be arranged in neutron detector simultaneously, certainly with offseting signal line
The noise signal of body improves detector sensitivity.
12, simple in structure, firm, small, it can preferably adapt to complex environment in heap.It present invention can be suitably applied to nuclear power station
Reactor core fuel assembly coolant enters, the temperature under outlet temperature and pressure vessels top cover measures, liquid level monitoring and reactor core
The measurement of neutron fluence rate, service life are long.
Description of the drawings
Fig. 1 is the overall structure diagram of the embodiment of the present invention 1；
Fig. 2 is the middle and lower parts Fig. 1 partial enlarged view；
Fig. 3 is in Fig. 1 along B-B sectional views；
Fig. 4 is the overall structure diagram of the embodiment of the present invention 2；
Fig. 5 is in Fig. 4 along A-A sectional views；
Fig. 6 is that level monitoring thermocouple is brazed schematic diagram with armoured thermocouple；
Fig. 7 is the armoured thermocouple schematic diagram in the embodiment of the present invention 2；
Fig. 8 is neutron detector schematic diagram.
Specific implementation mode
Below in conjunction with the accompanying drawings and specific implementation mode the invention will be further described.
Embodiment 1：
As shown in Figure 1 to Figure 3, a kind of used in nuclear power station in-pile instrument sheath assembly, including dust cover 1, electrical cnnector 2,
Rear shell 3, connecting tube 4, flexible metal conduit 5, collector upper connector 6, collector 7, connector 8, shell 9, armoured thermocouple 10, neutron
Detector 11, extended segment 12, extended segment connector 13, sub warhead end plug 14.
Armoured thermocouple 10 and branched neutron detector 11 are fixed with collector 7 by being brazed, armoured thermocouple 10 and neutron
Detector 11 is welded together with extended segment 12 and extended segment connector 13.Neutron detector 11 is self-power neutron detector, by sending out
Beam, collection body, insulator and cable form, and one 11 length of neutron detector of longest corresponds to whole in branched neutron detector 11
A reactor core height, remaining 11 length of neutron detector with 11 length of longest neutron detector by equidistantly successively decrease or in
11 length of sub- detector is identical, is equally spaced in an axial direction.
Collector 7 is welded by collector upper connector 6 and flexible metal conduit 5, and 7 other end of collector passes through connector 8 and shell 9
Be welded to connect, flexible metal conduit 5 is welded by connecting tube 4 and rear shell 3, armoured thermocouple 10 and 11 lead of neutron detector with
2 terminal of electrical cnnector welds, and rear shell 3 is welded with electrical cnnector 2, and dust cover 1 is screwed in rear shell 3, and collector 7 passes through connector 8
It is welded with shell 9, shell 9 is welded with sub warhead end plug 14, and sub warhead end plug 14 welds end socket after shell 9 fills helium.
Embodiment 2：
As shown in Fig. 2 to Fig. 8, difference lies in the one or more armoured thermocouples 10 of setting with embodiment 1 for embodiment 2, separately
It is outer that one or more level monitoring thermocouple 15 is set.Level monitoring thermocouple 15 is fixed on one with the soldering of armoured thermocouple 10 16
It rises (Fig. 6)
For monitoring fuel assembly entrance coolant temperature measuring point, fuel assembly fuel element goes out branched armoured thermocouple 10
Mouth temperatures at localized regions measuring point, fuel assembly TBC outlet temperatures measuring point and the inferior temperature point of reactor lid.
Level monitoring thermocouple 15 is composed by electrified heating device TPIU and without the thermocouple TP of electric heater, just
Under normal operating mode, electrified heating device TPIU and the thermocouple TP without electric heater are in coolant, due to liquid thermal conductivity
Can be good, therefore electrified heating device TPIU and smaller without the temperature difference between the thermocouple TP of electric heater, it not will produce alarm signal.When
When refrigerant level in pressure vessel reduces for some reason, when some electrified heating device TPIU is in gas phase media,
Since air conduction performance ratio liquid is poor, the temperature of electrified heating device TPIU can steeply rise, thus with still in cold
But the thermoelectric in agent also drastically becomes larger, and when difference is more than warning level, just provides alarm.Due to electrified heating device TPIU
It is fixed with the thermocouple TP installation sites without electric heater, therefore can be charged and be added by temperature difference alarm signal accurate judgement
Hot device TPIU corresponding refrigerant levels when being in gas phase thermal medium.Under accident conditions, such as primary pipe rupture, make coolant
Liquid level drastically declines, so that in air, at this moment the thermocouple TP without electric heater in extreme lower position also exposes
Provide accident conditions limit inferior liquid level warning.
As shown in figure 8, a background signal line 17 and a corresponding signal wire 18 is arranged in neutron detector 11, it is used for
The offseting signal line noise signal of itself improves detector sensitivity.
Claims (4)
1. a kind of used in nuclear power station in-pile instrument sheath assembly, including armoured thermocouple (10), collector (7), neutron detector (11),
Extended segment (12), extended segment connector (13), it is characterised in that：At least an armoured thermocouple (10) and branched neutron detector
(11) it is fixed together by collector (7) soldering, an at least level monitoring thermocouple (15) is brazed with armoured thermocouple (10)
It is fixed together, the neutron detector (11) is self-power neutron detector, by emitter, collects body, insulator and cable
It forming, one neutron detector (11) length of longest corresponds to entire reactor core height in branched neutron detector (11),
Remaining neutron detector (11) length is with longest neutron detector (11) length by equidistantly successively decreasing or neutron detector (11) is long
It spends identical, is equally spaced in an axial direction；The extended segment (12) by extended segment connector (13) by armoured thermocouple (10) with it is branched
Neutron detector is bound to together；It is welded by collector upper connector (6) and flexible metal conduit (5) described collector (7) one end
Connection, collector (7) other end are welded to connect by connector (8) and shell (9), and shell (9) front end is welded with sub warhead end plug (14)
It connects in succession, sub warhead end plug (14) welds end socket after shell (9) fills helium；The level monitoring thermocouple (15) is added by electrification
It hot device TPIU and is composed without the thermocouple TP of electric heater, for the variation of refrigerant level in monitoring pressure container,
The information and the refrigerant level data under accident conditions that the various change trend of coolant is provided.
2. used in nuclear power station in-pile instrument sheath assembly according to claim 1, it is characterised in that：The flexible metal conduit
(5) it is welded to connect by connecting tube (4) and rear shell (3), rear shell (3) is welded to connect with electrical cnnector (2), is twisted in rear shell (3)
There are dust cover (1), armoured thermocouple (10) and neutron detector (11) lead to be welded to connect with electrical cnnector (2) terminal.
3. used in nuclear power station in-pile instrument sheath assembly according to claim 1, it is characterised in that：The branched thermocouple
(10) be used to monitor fuel assembly entrance coolant temperature measuring point, fuel assembly fuel element outlet temperatures at localized regions measuring point,
Temperature point under fuel assembly TBC outlet temperatures measuring point and reactor lid.
4. used in nuclear power station in-pile instrument sheath assembly according to claim 1, it is characterised in that：The neutron detector
(11) a background signal line and a corresponding signal wire are set, for the offseting signal line noise signal of itself, improved
Detector sensitivity.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201611050199.4A CN106531245B (en) | 2016-11-25 | 2016-11-25 | Used in nuclear power station in-pile instrument sheath assembly |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201611050199.4A CN106531245B (en) | 2016-11-25 | 2016-11-25 | Used in nuclear power station in-pile instrument sheath assembly |
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| CN106531245A CN106531245A (en) | 2017-03-22 |
| CN106531245B true CN106531245B (en) | 2018-11-13 |
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|---|---|---|---|---|
| CN107662060B (en) * | 2017-10-20 | 2020-02-11 | 中广核核电运营有限公司 | Method for treating thermocouple guide pipe leakage in reactor core measurement system and welding bracket |
| CN107767974B (en) * | 2017-11-14 | 2024-04-16 | 国核自仪系统工程有限公司 | Nuclear reactor core neutron and temperature detection device |
| CN108109709A (en) * | 2017-12-21 | 2018-06-01 | 中国原子能科学研究院 | High temperature ionization chamber suspension arrangement in heap |
| CN108269634A (en) * | 2018-01-17 | 2018-07-10 | 上海核工程研究设计院有限公司 | A kind of used in nuclear power station includes the in-pile instrument sheath assembly of isometric arrangement detector |
| CN110111917B (en) * | 2019-04-17 | 2020-11-06 | 中广核工程有限公司 | Method and device for monitoring neutron flux of out-of-reactor nuclear reactor after accident and readable storage medium |
| CN111175808B (en) * | 2020-01-02 | 2022-06-28 | 中国原子能科学研究院 | Assembly and testing method based on assembly |
| CN112331373A (en) * | 2020-11-03 | 2021-02-05 | 浙江伦特机电有限公司 | Fast response nuclear reactor core temperature measurement assembly |
| CN112652412B (en) * | 2020-12-18 | 2023-01-20 | 中广核研究院有限公司 | Nuclear power station neutron and temperature monitoring device |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1080776A (en) * | 1992-06-22 | 1994-01-12 | 西屋电气公司 | Fixed incore detector |
| CN1477648A (en) * | 2002-08-21 | 2004-02-25 | 中国核动力研究设计院 | Core level monitoring device for reactor |
| CN103871526A (en) * | 2012-12-14 | 2014-06-18 | 中国核动力研究设计院 | Detection apparatus for neutron flux and temperature of reactor core |
| CN105247619A (en) * | 2013-05-29 | 2016-01-13 | 韩国水力原子力株式会社 | Convergence reactor in-core detector assembly for core monitoring and protection |
| CN105373698A (en) * | 2015-10-14 | 2016-03-02 | 中科华核电技术研究院有限公司 | Method for eliminating signal time delay of self-powered neutron detector |
| CN105387948A (en) * | 2014-08-25 | 2016-03-09 | 韩国水力原子力（株） | Multi-thermocouple in-core instrument assembly and system and method for monitoring nuclear reactor |
| CN105513657A (en) * | 2015-12-14 | 2016-04-20 | 中广核工程有限公司 | Nuclear power plant integrated in-core instrumentation assembly |
| CN206194382U (en) * | 2016-11-25 | 2017-05-24 | 浙江伦特机电有限公司 | Reactor core appearance gauge sleeve pipe assembly for nuclear power station |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103985422B (en) * | 2014-03-20 | 2017-03-01 | 中国核动力研究设计院 | Based on the active of 177 reactor cores plus passive nuclear steam supply system and its nuclear power station |
-
2016
- 2016-11-25 CN CN201611050199.4A patent/CN106531245B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1080776A (en) * | 1992-06-22 | 1994-01-12 | 西屋电气公司 | Fixed incore detector |
| CN1477648A (en) * | 2002-08-21 | 2004-02-25 | 中国核动力研究设计院 | Core level monitoring device for reactor |
| CN103871526A (en) * | 2012-12-14 | 2014-06-18 | 中国核动力研究设计院 | Detection apparatus for neutron flux and temperature of reactor core |
| CN105247619A (en) * | 2013-05-29 | 2016-01-13 | 韩国水力原子力株式会社 | Convergence reactor in-core detector assembly for core monitoring and protection |
| CN105387948A (en) * | 2014-08-25 | 2016-03-09 | 韩国水力原子力（株） | Multi-thermocouple in-core instrument assembly and system and method for monitoring nuclear reactor |
| CN105373698A (en) * | 2015-10-14 | 2016-03-02 | 中科华核电技术研究院有限公司 | Method for eliminating signal time delay of self-powered neutron detector |
| CN105513657A (en) * | 2015-12-14 | 2016-04-20 | 中广核工程有限公司 | Nuclear power plant integrated in-core instrumentation assembly |
| CN206194382U (en) * | 2016-11-25 | 2017-05-24 | 浙江伦特机电有限公司 | Reactor core appearance gauge sleeve pipe assembly for nuclear power station |
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| CN106531245A (en) | 2017-03-22 |
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Address after: 325608 No.1, Chengdong Road, science and Technology Park, Hongqiao Town, Yueqing City, Wenzhou City, Zhejiang Province Patentee after: ZHEJIANG LUNTE ELECTROMECHANICAL CO.,LTD. Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: 325608 No.1, Chengdong Road, science and Technology Park, Hongqiao Town, Yueqing City, Wenzhou City, Zhejiang Province Patentee before: ZHEJIANG LUNTE ELECTROMECHANICAL CO.,LTD. Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Address after: 325608 No.1, Chengdong Road, science and Technology Park, Hongqiao Town, Yueqing City, Wenzhou City, Zhejiang Province Patentee after: ZHEJIANG LUNTE ELECTROMECHANICAL CO.,LTD. Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: 325608 No.1, Chengdong Road, science and Technology Park, Hongqiao Town, Yueqing City, Wenzhou City, Zhejiang Province Patentee before: ZHEJIANG LUNTE ELECTROMECHANICAL CO.,LTD. Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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