CN112102974A - Height measuring device for control rod driving rod of nuclear reactor - Google Patents

Height measuring device for control rod driving rod of nuclear reactor Download PDF

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Publication number
CN112102974A
CN112102974A CN202010962373.2A CN202010962373A CN112102974A CN 112102974 A CN112102974 A CN 112102974A CN 202010962373 A CN202010962373 A CN 202010962373A CN 112102974 A CN112102974 A CN 112102974A
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CN
China
Prior art keywords
rod
assembly
connecting rod
intermediate connecting
measuring device
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202010962373.2A
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Chinese (zh)
Inventor
周围
张大为
范伟丰
孟维民
唐超
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
CNNC Nuclear Power Operation Management Co Ltd
Nuclear Power Qinshan Joint Venture Co Ltd
Original Assignee
CNNC Nuclear Power Operation Management Co Ltd
Nuclear Power Qinshan Joint Venture Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by CNNC Nuclear Power Operation Management Co Ltd, Nuclear Power Qinshan Joint Venture Co Ltd filed Critical CNNC Nuclear Power Operation Management Co Ltd
Priority to CN202010962373.2A priority Critical patent/CN112102974A/en
Publication of CN112102974A publication Critical patent/CN112102974A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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 invention relates to a height measuring device for a control rod driving rod of a nuclear reactor, which consists of an upper component 1, a middle component 2 and a lower component 3, wherein the upper component 1, the middle component 2 and the lower component 3 are sequentially connected to form a hollow structure, measuring core rods capable of freely sliding are arranged in the upper component 1, the middle component 2 and the lower component 3, and the measuring core rods in the upper component 1 are used for calibrating scale values. The height measuring device for the control rod driving rod of the nuclear reactor, provided by the invention, can accurately measure the absolute height of the control rod driving rod assembly in the reactor core installation through the design of the measuring tool with a pure mechanical structure, namely the absolute height value of the upper end surface of the driving rod assembly relative to the upper end surface of the control rod guide cylinder assembly, so that the connection state of the control rod driving rod assembly can be directly judged, and the height measuring device can be used for underwater remote measurement.

Description

Height measuring device for control rod driving rod of nuclear reactor
Technical Field
The invention belongs to the technical field of nuclear reactor control rod drive rod inspection, and particularly relates to a height measuring device for a nuclear reactor control rod drive rod.
Background
During field installation, reactor shutdown refueling and in-service inspection of a pressurized water reactor nuclear power station, a control rod drive rod assembly and a control rod assembly are unlocked (tripped and connected), and in order to ensure safety, whether unlocking is in place or not is checked.
During shutdown refueling and in-service inspection, the reactor cavity has strong radioactivity, operators cannot approach the reactor cavity, the control rod assembly is located 4 meters more below the water surface of the reactor cavity refueling water pool, and when the control rod driving rod is inspected to be unlocked in place, the operators can only carry out long-distance underwater operation, so that the difficulty is high.
The invention aims to provide a height measuring device for a control rod driving rod of a nuclear reactor, which directly measures the height of the driving rod extending out of the upper end surface of an upper reactor internals.
Disclosure of Invention
The invention aims to provide a height measuring device for a control rod driving rod of a nuclear reactor, which can directly measure the absolute height value of the upper end surface of a driving rod assembly relative to the upper end surface of a guide cylinder assembly, does not need indirect conversion, and can also check the abnormity of the mounting and matching process of the control rod assembly and an upper reactor internals.
The height measuring device for the control rod driving rod of the nuclear reactor comprises an upper assembly, a middle assembly and a lower assembly, wherein the upper assembly, the middle assembly and the lower assembly are sequentially connected to form a hollow structure, measuring core rods capable of freely sliding are arranged in the upper assembly, the middle assembly and the lower assembly, and the measuring core rods in the upper assembly are calibrated to scale values.
During measurement, the lower end of the measuring core rod in the lower assembly is in contact with the upper end of the driving rod, the height of the driving rod is upwards transmitted to the measuring core rod in the upper assembly, and reading is carried out through the scale value calibrated by the measuring core rod in the upper assembly, so that the absolute height of the driving assembly in reactor core installation can be accurately measured.
Preferably, the upper assembly, the middle assembly and the lower assembly are detachably connected in sequence.
Preferably, the upper assembly, the middle assembly and the lower assembly are sequentially in threaded connection.
Preferably, the scale value is calibrated by using a long rod simulator with known dimensions.
Preferably, the long rod simulator is a simulator of a driving rod.
Preferably, the reference of the scale value is the height value of the head of the driving rod relative to the upper end surface of the control rod guide cylinder when the lock is unlocked in place, and the change range of the scale value is within 10 cm.
Preferably, the upper portion subassembly comprises rings, measurement scale, guide holder, grab the pole and upper portion subassembly locking swivel nut, rings respectively with grab the pole and the guide holder is connected, the guide holder is connected with upper portion subassembly locking swivel nut and is formed hollow structure, the measurement scale lower extreme runs through the guide holder and is connected the hollow structure that forms with upper portion subassembly locking swivel nut.
Preferably, the suspension ring comprises an arcuate bar and a cross bar.
Preferably, the outer ends of two ports of the arched rod are connected with the grabbing rod, and the cross rod is connected with the guide seat.
Preferably, the middle assembly is formed by connecting a plurality of middle connecting rods.
Preferably, the middle assembly is formed by connecting a plurality of middle connecting rods in a threaded manner.
Preferably, the middle assembly is formed by connecting 2 middle connecting rods in a threaded manner.
Preferably, the middle connecting rod is composed of a middle connecting rod threaded sleeve, a hook, a middle connecting rod measuring core rod, a middle connecting rod locking threaded sleeve and a middle connecting rod outer rod, the middle connecting rod threaded sleeve, the hook, the middle connecting rod outer rod and the middle connecting rod locking threaded sleeve are sequentially connected to form a hollow structure, and the middle connecting rod measuring core rod freely slides in the hollow structure formed by sequentially connecting the middle connecting rod threaded sleeve, the hook, the middle connecting rod outer rod and the middle connecting rod locking threaded sleeve.
Preferably, the lower assembly consists of a lower assembly measuring core rod, a lower assembly threaded sleeve, a lower assembly outer rod and a bell mouth, the lower assembly threaded sleeve, the lower assembly outer rod and the bell mouth are sequentially connected to form a hollow structure, and the lower assembly measuring core rod freely slides in the hollow structure formed by sequentially connecting the lower assembly threaded sleeve, the lower assembly outer rod and the bell mouth.
Preferably, the measuring scale, the middle connecting rod measuring core rod and the lower component measuring core rod are limited by an internal stop structure.
Preferably, the middle connecting rod thread bushing and the lower component thread bushing are matched with the upper component locking thread bushing and the middle connecting rod locking thread bushing.
The invention has the beneficial technical effects that:
according to the height measuring device for the control rod driving rod of the nuclear reactor, provided by the invention, through the design of the measuring tool with a pure mechanical structure, the upper component, the middle component and the lower component can be quickly connected to form a hollow structure, measuring core rods capable of freely sliding are arranged in the upper component, the middle component and the lower component, and the measuring core rods in the upper component are calibrated with scale values, so that the height of the driving rod component can be transmitted to the measuring core rods of the upper component for reading, the absolute height of the control rod driving rod component in the reactor core installation can be accurately measured, namely the absolute height value of the upper end surface of the driving rod component relative to the upper end surface of the control rod guide cylinder component, the connection state of the control rod driving rod component can be directly.
Drawings
Fig. 1 is a schematic view of a drive rod installation.
Fig. 2 is a schematic structural diagram of a height measuring device for a control rod driving rod of a nuclear reactor according to the present invention.
Fig. 3 is a schematic view of the upper assembly structure.
Fig. 4 is a schematic view of the structure of the intermediate connecting rod.
Fig. 5 is a schematic view of the structure of the lower assembly.
Fig. 6 is a schematic view of the structure of the hanging ring.
Wherein:
1-upper component, 2-middle connecting rod, 3-lower component;
11-a lifting ring, 12-a measuring scale, 13-a grabbing rod, 14-an upper component locking threaded sleeve and a guide seat 15;
21-middle connecting rod thread bushing, 22-hook, 23-middle connecting rod measuring core rod, 24-middle connecting rod locking thread bushing and 25-middle connecting rod outer rod;
31-lower component measuring core rod, 32-lower component thread bushing, 33-lower component outer rod and 34-bell mouth;
111-bow bar, 112-cross bar.
Detailed Description
In the description of the present invention, it is to be understood that the terms "upper end", "lower end", "upper", "middle", "lower", and the like indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of description and simplicity of description, and do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and be operated, and thus, should not be construed as limiting the present invention. Furthermore, the terms "a", "an", and "the" mean two or more unless explicitly limited otherwise.
Referring to fig. 2, the invention provides a height measuring device for a control rod driving rod of a nuclear reactor, which comprises an upper assembly 1, a middle assembly and a lower assembly 3, wherein the middle assembly is formed by connecting a plurality of middle connecting rods 2 in a threaded manner, and the upper assembly 1, the middle assembly and the lower assembly 3 are sequentially connected in a threaded manner to form a hollow structure.
Join in fig. 3, upper assembly 1 comprises rings 11, measurement scale 12, guide holder 15, grab bar 13 and upper assembly locking swivel nut 14, rings 11 include bow-shaped rod 111 and horizontal pole 112, bow-shaped rod 111 both ends mouth outer end is connected with grab bar 12, horizontal pole 112 is connected with guide holder 15, guide holder 15 is connected with upper assembly locking swivel nut 14 and forms hollow structure, the hollow structure that formation is connected with upper assembly locking swivel nut 14 to measurement scale 12 lower extreme through guide holder 15.
Referring to fig. 4, the intermediate connecting rod 2 is composed of an intermediate connecting rod thread bushing 21, a hook 22, an intermediate connecting rod measuring core rod 23, an intermediate connecting rod locking thread bushing 24 and an intermediate connecting rod outer rod 25, the intermediate connecting rod thread bushing 21, the hook 22, the intermediate connecting rod outer rod 25 and the intermediate connecting rod locking thread bushing 24 are sequentially connected to form a hollow structure, and the intermediate connecting rod measuring core rod 23 freely slides in the hollow structure formed by sequentially connecting the intermediate connecting rod thread bushing 21, the hook 22, the intermediate connecting rod outer rod 25 and the intermediate connecting rod locking thread bushing 24.
Referring to fig. 5, the lower assembly is composed of a lower assembly measuring core rod 31, a lower assembly threaded sleeve 32, a lower assembly outer rod 33 and a bell mouth 34, the lower assembly threaded sleeve 32, the lower assembly outer rod 33 and the bell mouth 34 are sequentially connected to form a hollow structure, and the lower assembly measuring core rod 31 freely slides in the hollow structure formed by sequentially connecting the lower assembly threaded sleeve 32, the lower assembly outer rod 33 and the bell mouth 34.
The middle connecting rod thread bushing 21 and the lower component thread bushing 32 are respectively matched with the upper component locking thread bushing 14 and the middle connecting rod locking thread bushing 24 to form threaded connection.
The measuring scale 12, the middle connecting rod measuring core rod 23 and the lower component measuring core rod 31 are limited by an internal stop structure.
The intermediate connecting rod outer rod 25 and the lower assembly outer rod 33 are used for support and positioning of the profile.
During assembly, the height of each component is designed and adjusted according to actual conditions, and the hook 22 is hung on the supporting equipment so as to assemble the upper component 1, the middle component 2 and the lower component 3 into the height measuring device of the control rod driving rod of the nuclear reactor in sequence.
After the assembly is finished, the scale value of the measuring scale 12 is calibrated by using a simulator of the driving rod with known size, the reference of the scale value is the height value of the head of the driving rod relative to the upper end surface of the control rod guide cylinder when the driving rod is unlocked in place, and the change range of the scale value is within 10 cm.
When the height measuring device is used, the height measuring device for the control rod drive rod of the nuclear reactor is covered above the drive rod to be measured, and the hanging ring 11 is connected with the crane for hoisting and is used for controlling the movement and rotation of the height measuring device and reading data. The horn mouth 34 plays a guiding role in covering the driving rod to be measured, the driving rod to be measured is conveniently and easily guided into the height measuring device during alignment, the alignment efficiency of the height measuring device is improved, and in addition, the end face of the horn mouth is contacted with the upper end face of the driving rod assembly to play a role in measuring a reference. The upper end of the driving rod to be measured is contacted with the lower end of the lower component measuring core rod 31, the upper end of the lower component measuring core rod 31 is contacted with the lower end of the middle connecting rod measuring core rod 23, the upper end of the middle connecting rod measuring core rod 23 is contacted with the lower end of the measuring scale 12, so that the height value of the driving rod is transmitted to the measuring scale 12, and finally the absolute height of the control rod driving rod assembly in the reactor core installation, namely the absolute height value of the upper end surface of the driving rod assembly relative to the upper end surface of the control rod guide cylinder assembly, is read from.
The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the scope of the present invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.

Claims (10)

1. The height measuring device for the control rod driving rod of the nuclear reactor comprises an upper assembly, a middle assembly and a lower assembly, wherein the upper assembly, the middle assembly and the lower assembly are sequentially connected to form a hollow structure, measuring core rods capable of freely sliding are arranged in the upper assembly, the middle assembly and the lower assembly, and the measuring core rods in the upper assembly are calibrated to scale values.
2. The height measuring device of claim 1, wherein the upper assembly, the middle assembly, and the lower assembly are removably connected in sequence.
3. The height measuring device of claim 1 or 2, wherein the scale value is calibrated with a long rod phantom of known dimensions.
4. The height measuring device according to any one of claims 1 to 3, wherein the upper assembly is composed of a hanging ring, a measuring scale, a guide seat, a grabbing rod and an upper assembly locking threaded sleeve, the hanging ring is respectively connected with the grabbing rod and the guide seat, the guide seat is connected with the upper assembly locking threaded sleeve to form a hollow structure, and the lower end of the measuring scale penetrates through the hollow structure formed by connecting the guide seat with the upper assembly locking threaded sleeve.
5. The height measuring device of any one of claims 1-4, wherein the middle assembly is formed by a plurality of middle connecting rods that are connected by threads.
6. The height measuring device of claim 5, wherein the mid-section assembly is threaded with 2 intermediate connecting rods.
7. The height measuring device according to claim 5 or 6, wherein the intermediate connecting rod is composed of an intermediate connecting rod thread bushing, a hook, an intermediate connecting rod measuring core rod, an intermediate connecting rod locking thread bushing and an intermediate connecting rod outer rod, the intermediate connecting rod thread bushing, the hook, the intermediate connecting rod outer rod and the intermediate connecting rod locking thread bushing are sequentially connected to form a hollow structure, and the intermediate connecting rod measuring core rod freely slides in the hollow structure formed by the sequential connection of the intermediate connecting rod thread bushing, the hook, the intermediate connecting rod outer rod and the intermediate connecting rod locking thread bushing.
8. The height measuring device of any one of claims 1-7, wherein the lower assembly is comprised of a lower assembly measuring core rod, a lower assembly threaded sleeve, a lower assembly outer rod, and a bell mouth, the lower assembly threaded sleeve, the lower assembly outer rod, and the bell mouth are connected in series to form a hollow structure, and the lower assembly measuring core rod is free to slide in the hollow structure formed by the lower assembly threaded sleeve, the lower assembly outer rod, and the bell mouth in series.
9. The height measuring device of claim 8, wherein the measuring scale, the intermediate connecting rod measuring core rod, and the lower assembly measuring core rod are each retained by an internal stop structure.
10. The height measuring device of claim 8 or 9, wherein the intermediate connecting rod thread insert and the lower assembly thread insert are adapted to the upper assembly locking thread insert and the intermediate connecting rod locking thread insert, respectively.
CN202010962373.2A 2020-09-14 2020-09-14 Height measuring device for control rod driving rod of nuclear reactor Pending CN112102974A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202010962373.2A CN112102974A (en) 2020-09-14 2020-09-14 Height measuring device for control rod driving rod of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202010962373.2A CN112102974A (en) 2020-09-14 2020-09-14 Height measuring device for control rod driving rod of nuclear reactor

Publications (1)

Publication Number Publication Date
CN112102974A true CN112102974A (en) 2020-12-18

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Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH085778A (en) * 1994-06-20 1996-01-12 Toshiba Corp Dimension and shape measuring device for control rod drive mechanism housing placement part and the like
JPH10213692A (en) * 1997-01-30 1998-08-11 Mitsubishi Heavy Ind Ltd Measurement device for control rod guide tube deformation of nuclear reactor fuel assembly
KR20060134536A (en) * 2005-06-23 2006-12-28 한전기공주식회사 Height measurement device of control rod drive shaft
CN101783188A (en) * 2009-01-21 2010-07-21 中国核电工程有限公司 Unlocking device for control rod drive lever
CN102483962A (en) * 2009-06-10 2012-05-30 巴布科克和威尔科克斯核作业集团股份有限公司 Control rod drive mechanism for nuclear reactor
CN103500524A (en) * 2013-09-29 2014-01-08 中广核工程有限公司 Cold test device and method for control rod drive line of nuclear power plant
CN110828015A (en) * 2019-11-14 2020-02-21 中核核电运行管理有限公司 Remote emergency operation tool and operation method for heavy water reactor nuclear power station material loading and unloading machine
CN214428339U (en) * 2020-09-14 2021-10-19 中核核电运行管理有限公司 Height measuring device for control rod driving rod of nuclear reactor

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH085778A (en) * 1994-06-20 1996-01-12 Toshiba Corp Dimension and shape measuring device for control rod drive mechanism housing placement part and the like
JPH10213692A (en) * 1997-01-30 1998-08-11 Mitsubishi Heavy Ind Ltd Measurement device for control rod guide tube deformation of nuclear reactor fuel assembly
KR20060134536A (en) * 2005-06-23 2006-12-28 한전기공주식회사 Height measurement device of control rod drive shaft
CN101783188A (en) * 2009-01-21 2010-07-21 中国核电工程有限公司 Unlocking device for control rod drive lever
CN102483962A (en) * 2009-06-10 2012-05-30 巴布科克和威尔科克斯核作业集团股份有限公司 Control rod drive mechanism for nuclear reactor
CN103500524A (en) * 2013-09-29 2014-01-08 中广核工程有限公司 Cold test device and method for control rod drive line of nuclear power plant
CN110828015A (en) * 2019-11-14 2020-02-21 中核核电运行管理有限公司 Remote emergency operation tool and operation method for heavy water reactor nuclear power station material loading and unloading machine
CN214428339U (en) * 2020-09-14 2021-10-19 中核核电运行管理有限公司 Height measuring device for control rod driving rod of nuclear reactor

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