CN107945890B - Nuclear power station reactor control rod driving mechanism - Google Patents
Nuclear power station reactor control rod driving mechanism Download PDFInfo
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- CN107945890B CN107945890B CN201711348475.XA CN201711348475A CN107945890B CN 107945890 B CN107945890 B CN 107945890B CN 201711348475 A CN201711348475 A CN 201711348475A CN 107945890 B CN107945890 B CN 107945890B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
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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 nuclear power station reactor control rod driving mechanism which comprises a pressure-resistant shell assembly, a claw assembly, a driving rod assembly, a coil assembly and a rod position detector assembly, wherein the pressure-resistant shell assembly is an integrated shell, the top of the pressure-resistant shell assembly is of a blind pipe structure, and the bottom of the pressure-resistant shell assembly is detachably and hermetically arranged on a CRDM pipe seat of a top cover of a pressure vessel through threaded connection. Compared with the prior art, the reactor control rod driving mechanism of the nuclear power station adopts the integrated pressure shell component, no welding seam is arranged on the pressure shell component, and the pressure shell component and the CRDM pipe seat are connected by screw threads and sealed by a pair of sealing rings, so that the risk of leakage of a reactor coolant can be effectively reduced. In addition, the hook component adopts a double-tooth hook structure, so that the wear resistance of the hook can be greatly improved, the service life of the control rod driving mechanism is prolonged, the hook component is assembled and disassembled from the bottom of the pressure-resistant shell component, and the irradiation injury risk to operators can be reduced.
Description
Technical Field
The invention belongs to the field of pressurized water reactor nuclear power plants, and particularly relates to a reactor control rod driving mechanism of a nuclear power plant.
Background
A Control Rod Drive Mechanism (CRDM) is a vertically stepped magnetic lifting device mounted on the top head of a reactor pressure vessel. As important equipment for executing reactivity control, the CRDM can drive the control rod assembly to move up and down within the range of the reactor core and keep at the command height according to the command, or the power-off release rod enables the control rod to be inserted into the reactor core under the action of gravity, so that the functions of controlling the startup, power regulation and shutdown of the reactor are achieved. Additionally, the CRDM pressure housing acts as a primary pressure boundary for coolant contact and is a radiation containment safety barrier.
Currently, commonly used CRDMs mainly include: the device comprises a pressure shell assembly, a claw assembly, a driving rod assembly, a coil assembly and a rod position detector assembly. The pressure shell assembly must be able to withstand high temperatures and pressures, be part of the reactor primary coolant system pressure boundary, and ensure the integrity of the reactor pressure boundary and the absence of any coolant leakage. The hook component is a CRDM movement executing component and comprises an upper hook movement pair and a lower hook movement pair, and CRDM movement can be realized through ordered matching of the two hook movement pairs. The bottom of the drive rod component is connected with the control rod, the outer surface of the drive rod component is provided with a ring groove, and the ring groove is matched with the hook claw to drive the control rod to ascend or descend. The coil assembly mainly comprises three coils and a magnetic yoke and is arranged outside the pressure shell assembly. The rod position detector assembly is used for detecting the position of the driving rod, comprises a primary coil and a secondary coil and is installed on the outer side of the rod stroke sleeve. In addition, the stack top is also provided with a ventilation cooling device to realize the cooling of the coil assembly.
In the prior art, a CRDM pressure-resistant shell is composed of three sections, namely an end plug, a rod stroke sleeve and a hook shell from top to bottom, wherein the bottom of the pressure-resistant shell is arranged on a CRDM tube seat of a top cover of a pressure vessel. The mutual connection parts are connected by screw threads and sealed by omega welding seams, so the CRDM pressure housing has upper, middle and lower omega welding seams.
The claw assembly is arranged in the claw shell, the lifting magnetic pole of the claw assembly is fixed on the upper end boss of the claw shell and is pressed by the rod stroke sleeve, and the lower end of the claw assembly is positioned in an auxiliary mode. During assembly, the claw assembly is assembled from the top of the claw shell.
The actuating rod member is located within the pressure shell assembly and extends through the finger assembly, and is connected at its lower end to the control rod assembly by a releasable joint.
The rod travel sleeve provides space for the drive rod assembly to move up and down.
The coil assembly is sleeved outside the hook claw shell, 3 coils of the coil assembly, magnetic poles corresponding to the hook claw assembly and armatures form 3 electromagnets, and the electromagnets are respectively a lifting electromagnet, a moving electromagnet and a fixed electromagnet from top to bottom. When the 3 electromagnets are electrified according to a given program, the driving rod part can move up and down or be still, and when the power is off, the rod falls.
The rod position detector assembly adopts a group of primary coils and secondary coils and is a single-precision rod position detector.
However, the above-mentioned conventional CRDM has the following drawbacks:
1) the sealing method has the advantages that three omega-shaped sealing welding seams are formed, the omega-shaped sealing welding seams are thin-wall welding seams, the thickness is 1.9-2.3 mm, damage and leakage accidents easily occur in an omega-shaped welding seam area, and the risk of damage and leakage is large.
2) The single-precision rod position detector has low measurement precision and low reliability, and does not meet a single fault criterion.
3) The coil has large electrifying current and poor temperature resistance of the coil material, so ventilation and cooling are needed.
In order to overcome the above-mentioned drawbacks, the related art makes improvements to CRDM: the CRDM pressure-resistant shell comprises two sections, wherein the upper part is a rod stroke sleeve, and the lower part is a claw shell. The rod stroke sleeve is an integrated piece, the top end of the rod stroke sleeve is of a blind pipe structure, the hook claw shell and the CRDM pipe seat are integrated into an integrated piece, and the rod stroke sleeve is connected with the hook claw shell through threads and sealed through omega welding seams.
The CRDM gripper assembly is suspended from the rod travel sleeve bottom. During assembly, the finger assembly is loaded from the top of the finger housing. And (3) in the in-service stage of the reactor, if the hook component needs to be maintained and replaced, cutting the omega-shaped welding line, and lifting the hook component out of the hook shell.
However, the above CRDM still has the following drawbacks:
1) the omega-shaped sealing weld joint is positioned between the rod stroke sleeve and the hook claw shell, when the hook claw assembly is disassembled, the hook claw assembly is lifted out of the hook claw shell, the hook claw assembly polluted by the reactor coolant has radioactivity, and the hook claw assembly is exposed in the environment after being lifted out to generate irradiation injury risks to operators.
2) The coil has large electrifying current, the temperature resistance of the coil material is poor, and ventilation and cooling are also needed.
In view of the above, it is necessary to provide a safe and reliable control rod driving mechanism for a nuclear power plant reactor.
Disclosure of Invention
The invention aims to: the defects of the prior art are overcome, and the safe and reliable nuclear power station reactor control rod driving mechanism is provided.
In order to achieve the aim, the invention provides a reactor control rod driving mechanism of a nuclear power station, which comprises a pressure-resistant shell assembly, a claw assembly, a driving rod assembly, a coil assembly and a rod position detector assembly, wherein the pressure-resistant shell assembly is an integrated shell, the top of the pressure-resistant shell assembly is of a blind pipe structure, and the bottom of the pressure-resistant shell assembly is detachably and hermetically arranged on a CRDM pipe seat of a top cover of a pressure vessel.
As an improvement of the nuclear power station reactor control rod driving mechanism, a sealing ring is arranged between the pressure shell assembly and the CRDM pipe seat.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, the sealing ring is a C-shaped sealing ring or an O-shaped sealing ring provided with a through hole.
As an improvement of the nuclear power station reactor control rod driving mechanism, the sealing ring is a spring C-shaped sealing ring.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, the sealing ring is made of nickel-based alloy, and the surface of the sealing ring is plated with silver.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, the sealing ring comprises an inner ring sealing ring and an outer ring sealing ring.
As an improvement of the nuclear power station reactor control rod driving mechanism, the hook component is arranged in the pressure shell component from the bottom of the pressure shell component, and the lower end of the hook component is supported on a CRDM tube seat of a top cover of a pressure vessel through a limiting nut.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, the hook component adopts a double-tooth hook.
As an improvement of the nuclear power station reactor control rod driving mechanism, the coil assembly is sleeved at the lower part of the pressure shell assembly and comprises 3 electromagnetic coils, a magnet yoke, a lead wire and a wire conduit, the claw assembly is correspondingly provided with an iron core assembly, and the electromagnetic coils and the magnet yoke of the coil assembly and the iron core assembly correspondingly arranged on the claw assembly form a lifting electromagnet, a moving electromagnet and a fixed electromagnet from top to bottom.
As an improvement of the nuclear power station reactor control rod driving mechanism, the lifting electromagnet is provided with a lifting armature, and an air gap of the lifting armature is 11-15 mm.
As an improvement of the nuclear power station reactor control rod driving mechanism, the upper part of the pressure shell component is provided with a step surface, the rod position detector component is supported on the step surface and comprises a positioning sleeve, an inner coil positioned in the positioning sleeve and close to the inner side, and an outer coil positioned in the positioning sleeve and close to the outer side.
As an improvement of the control rod driving mechanism of the nuclear power station reactor, the inner coil and the outer coil adopt a Gray code signal output mode.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, the inner coil and the outer coil can be matched with each other to realize double-precision design.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, the inner coil and the outer coil can work independently, and the redundant design is realized.
As an improvement of the reactor control rod drive mechanism of the nuclear power plant of the present invention, the pressure housing assembly is made of austenitic stainless steel.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, the bottom of the pressure shell component is detachably and hermetically arranged on a CRDM tube seat of a top cover of a pressure vessel through threaded connection.
As an improvement of the reactor control rod driving mechanism of the nuclear power station, an outer cover is arranged outside the rod position detector assembly and supported on the coil assembly.
Compared with the prior art, the nuclear power station reactor control rod driving mechanism has the following advantages:
1) the pressure-resistant shell is integrally arranged, no welding seam exists, the possibility of leakage of the reactor coolant can be reduced, in-service inspection is not required, and the operation and maintenance workload is reduced;
2) the pressure shell assembly is detachably connected with the CRDM tube seat through a threaded ring, the sealing ring can realize self-tightening sealing by using medium pressure, the sealing is reliable, the structure is simple, the disassembly is convenient and quick, and the replacement time and the irradiated dose of maintenance personnel can be reduced;
3) the double-tooth claw structure can improve the wear resistance of the claw and prolong the service life of the CRDM;
4) by optimizing the CRDM step length, increasing the number of turns of the coil, preparing an integrated pressure-resistant shell by adopting high-strength austenitic stainless steel (such as 06Cr18Ni11Nb) and using a thin-wall steel outer cover, the working current of the coil can be reduced, the heat productivity of the coil assembly is reduced, the coil assembly does not need ventilation and cooling, the stack top structure is simplified, and the economy of the nuclear power station is improved;
5) by adopting the double-precision rod position detector assembly, the measurement precision and accuracy of rod position detection are effectively improved, the rod position detection range is enlarged, the redundancy design is added, the accurate control of the reactor power of the nuclear power station is facilitated, and the safe operation of the nuclear power station is ensured.
6) The hook component is assembled and disassembled from the bottom of the pressure-resistant shell component, so that the risk of irradiation injury to operators can be reduced.
Drawings
The following describes the reactor control rod driving mechanism of a nuclear power plant and its technical effects in detail with reference to the accompanying drawings and the detailed description.
FIG. 1 is a schematic structural diagram of a nuclear power plant reactor control rod drive mechanism of the present invention.
FIG. 2 is a schematic view of the installation of a pressure housing assembly and a CRDM tube socket of the nuclear power plant reactor control rod drive mechanism of the present invention.
FIG. 3 is an assembly schematic diagram of a pressure housing assembly and a CRDM tube socket of the nuclear power plant reactor control rod drive mechanism of the present invention.
Fig. 4 is a partially enlarged schematic view of a circle portion a in fig. 3.
Fig. 5A to 5C are schematic structural diagrams of different embodiments of a seal ring in a reactor control rod drive mechanism of a nuclear power plant according to the present invention.
FIG. 6 is a schematic diagram of a hook assembly of a nuclear power plant reactor control rod drive mechanism according to the present invention.
Fig. 7 is a partially enlarged schematic view of a circle portion B in fig. 6.
FIG. 8 is a schematic diagram of a coil assembly of a nuclear power plant reactor control rod drive mechanism according to the present invention.
FIG. 9 is a schematic diagram of a rod position detector of a nuclear power plant reactor control rod drive mechanism according to the present invention.
FIG. 10 is a schematic diagram of the configuration of the housing of the control rod drive mechanism of a nuclear power plant reactor according to the present invention.
Detailed Description
In order to make the objects, technical solutions and advantageous technical effects of the present invention clearer, the present invention is further described in detail below with reference to the accompanying drawings and the detailed description. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1 to 10, the nuclear power plant reactor control rod driving mechanism of the present invention includes a pressure shell assembly 100, a hook assembly 200, a driving rod assembly 300, a coil assembly 400 and a rod position detector assembly 500, wherein the pressure shell assembly 100 is an integrated housing, the top of the pressure shell assembly is a blind pipe structure, and the bottom of the pressure shell assembly is detachably and hermetically mounted on a CRDM pipe seat of a top cover of a pressure vessel through threaded connection.
Referring to fig. 1 to 5, the pressure shell assembly 100 is an integrated shell without a welding structure. The top of the pressure housing assembly 100 is a blind pipe structure and the bottom is mounted on the pressure vessel top cover CRDM tube base 700. In the illustrated embodiment, the pressure housing assembly 100 and the pressure vessel top cover CRDM tube base 700 are connected by a threaded ring 102 to form a detachable sealed connection, and the threaded ring 102 is screwed on the CRDM tube base 700 to press the pressure housing assembly 100 against the CRDM tube base 700, and two C-shaped sealing rings 103 are used for sealing to form the detachable sealed connection. The surface of the C-shaped sealing ring 103 is plated with silver, so that the sealing performance can be improved.
When the threaded ring 102 is tightened, the C-ring 103 is compressed, establishing an initial seal; after the internal pressure of the pressure shell assembly 100 rises, the pressure shell assembly 100 and the CRDM tube seat 700 tend to be separated, and the C-shaped sealing ring 103 is also outwards expanded under the action of the internal pressure to realize self-locking sealing, so that the sealing effect is more reliable. In the illustrated embodiment, there are two C-shaped seal rings 103, which are divided into an inner ring seal ring and an outer ring seal ring, and when the inner ring seal ring fails, the outer ring seal ring can achieve the same sealing effect, thereby realizing double safety.
Referring to fig. 5A to 5C and fig. 7 in particular, according to other embodiments of the present invention, the sealing ring may be a spring C-shaped sealing ring 104 (a spring is disposed inside the C-shaped metal ring, and when the spring is compressed, the spring exerts a reverse force on the C-shaped metal ring to assist the C-shaped metal ring 104 in sealing, and the outer surface of the C-shaped metal ring is silver-plated), or an O-shaped sealing ring 105 with a through hole (made of a small metal circular tube, the outer surface of which is silver-plated, and a plurality of small holes are drilled inside the ring, so that the self-tightening sealing can be realized as the pressure in the tube increases with the increase of the pressure.
Referring to fig. 6 and 7, the finger assembly 200 is a movement executing assembly of the CRDM, and is composed of an upper finger kinematic pair and a lower finger kinematic pair, and the CRDM is implemented by orderly matching the two kinematic pairs. In the illustrated embodiment, the finger assembly 200 is installed in the pressure housing assembly 100 by being inserted into the bottom of the pressure housing assembly 100. The lower end of the hook component 200 is supported on a CRDM tube seat 700 of a top cover of the pressure vessel through a limiting nut 211 at the bottom, the upper end realizes radial positioning through the matching relation of the outer diameter of the lifting magnetic pole 201 and the inner diameter of the pressure resistant shell 100, and the upper end is axially unconstrained so as to ensure that the hook component can freely expand at high temperature.
In the illustrated embodiment, the quill 202 of the finger assembly 200 is the support shaft of the assembly, and has an upper end threaded to the lift pole 201 and a lower end threaded to a stop nut 211, the internal bore of which provides access and guidance for the drive rod assembly 300. Each part assembled on quill 202 may be divided into 3 subassemblies, each of which is an iron core assembly of 3 "electromagnets".
The core component of the lifting electromagnet comprises a lifting magnetic pole 201, an upper section of a lifting armature 203, and parts such as a buffer sheet, a magnetic separation sheet, a lifting spring and the like between the lifting magnetic pole and the upper section of the lifting armature.
The core assembly of the "moving electromagnet" includes the lower segment of the lifting armature 203, the magnetic separation sheet, the moving spring, the moving armature 204, the buffer shaft 205, and a subassembly composed of 3 sets of the hook 206 and the connecting rod 207.
The core assembly of the "fixed electromagnet" includes the fixed magnetic pole 208, the magnetic shielding sheet, the fixed spring, the fixed armature 209, the fixed claw support cylinder 210, and the subassembly of 3 sets of claws 213 and the connecting rod 214.
Before the CRDM is installed on the top cover, the hook assembly 200 is fixed inside the pressure housing 100 by three bolts 212 at the bottom, and then the integrated pressure housing 100 and hook assembly 200 are hung on the CRDM tube seat 700 together. After the finger assembly 200 is mounted on the pressure vessel top cover, the finger assembly 200 is supported on the CRDM header 700 of the pressure vessel top cover by the retaining nut 211 and is compressed by the boss inside the pressure housing 100. When disassembling, the pressure housing 100 and the finger assembly 200 are lifted out together, and the finger assembly 200 remains inside the pressure housing 100.
In the illustrated embodiment, the finger assembly 200 employs a double-tooth finger 206 configuration with two finger teeth disposed on each finger to increase the wear resistance of the fingers and thereby increase the operating life of the CRDM.
Referring to fig. 1, the driving lever member 300 includes a driving lever, a detachable joint, a detachable lever, a spring, and the like (not shown).
The drive rod assembly 300 is located within the pressure housing assembly 100 and passes through the finger assembly 200, and is connected at its lower end to the control rod assembly by a removable joint. The integrated pressure housing 100 provides a space for the driving rod assembly 300 to move up and down. The driving rod assembly 300 penetrates through the inner hole of the sleeve shaft 202 of the claw assembly 200, annular teeth are uniformly distributed on the driving rod and are matched with two sets of claw assemblies in the claw assembly 200 to move up and down in the integrated pressure-resistant shell 100, and lifting and downward insertion of the control rod assembly are realized.
Referring to FIG. 8, a coil assembly 400 is mounted on the lower portion of the pressure housing 100, and includes 3 electromagnetic coils 403, 404, 405, a yoke 402, lead wires, and a conduit 401. The electromagnetic coils 403, 404, 405 and the magnetic yoke 402 of the coil assembly 400 form 3 "electromagnets" together with the corresponding iron core assemblies of the claw assembly 200, and the "lifting electromagnet", "moving electromagnet" and "fixed electromagnet" respectively from top to bottom, and the action process is as follows:
the lifting coil 403 is electrified and excited to attract the lifting armature 202, so as to drive the movable claw 206 to lift by a step pitch; demagnetization opens the poppet armature 202, which resets the moving finger 206.
The moving coil 404 is electrified and excited to attract the moving armature 204, so that the connecting rod 207 is driven to move upwards, and the moving claw 206 swings into the annular groove of the driving rod and is meshed with the annular tooth of the driving rod; demagnetization opens the movable armature 204, drives the connecting rod 207 to descend, and swings the movable claw 206 out of the annular groove of the driving rod to be disengaged from the annular tooth of the driving rod.
The fixed coil 405 is electrified and excited to attract the fixed armature 209, so as to drive the connecting rod 214 to move upwards, and the fixed claw 213 swings into the annular groove of the driving rod and is engaged with the annular tooth of the driving rod; demagnetization opens the fixed armature 209, which causes the rod 214 to drop, causing the fixed hook 213 to swing out of the drive rod annular groove and disengage from the drive rod annular tooth.
Referring to FIG. 9, the rod position detector assembly 500 is sleeved on the upper portion of the pressure housing 100 and supported on the step surface of the pressure housing 100. The rod position detector assembly 500 is used to detect the actual position of the control rod assembly in the core and also to measure the rod drop time of the control rod assembly during a full stroke rod drop.
In the embodiment shown in FIG. 9, the rod position detector assembly 500 is provided with a positioning sleeve 502, an inner coil 504 located near the inside of the positioning sleeve 502, and an outer coil 506 located near the outside of the positioning sleeve 502. The inner coil 504 and the outer coil 506 adopt a gray code signal output mode, the inner coil 504 and the outer coil 506 work independently, double-precision redundancy design is achieved, and the measuring precision can reach +/-3 steps under the condition that the step length is not changed. When one of the inner coil 504 and the outer coil 506 can not work normally, the other coil can work independently, and the measurement precision is +/-6 steps. The prior art rod position detector assembly 500 has only a single layer coil with a measurement accuracy of + -4 steps. Compared with the prior art, the rod position detector assembly 500 can improve the measurement precision and accuracy of rod position detection, enlarge the rod position detection range, increase the redundancy design, facilitate the realization of accurate control of the reactor power of the nuclear power station, and ensure the safe operation of the nuclear power station.
Referring to fig. 1 and 10, the housing 600 has a cylindrical structure, is disposed outside the rod position detector assembly 500 and is supported on the coil part 400, and in the illustrated embodiment, the housing 600 is made of a thin steel plate.
In the illustrated embodiment, the housing 600 is made of thin-walled steel, which has a "chimney effect" and accelerates the gas flow inside the thin-walled steel housing 600, and takes away the heat generated by the coil assembly 400 through natural circulation, thereby reducing the temperature of the coil surface.
It should be noted that, in the prior art, since the coil assembly 400 generates a large amount of heat (the lifting coil 303 generates the largest amount of heat), and the maximum temperature that the coil can withstand is limited, a cooling and ventilating structure is required.
In order to reduce the heat productivity of the coil assembly 400 and eliminate a cooling ventilation device, the invention properly reduces the air gap (step length) of the lifting armature 203 and adjusts the step length to 11-15 mm. By such an arrangement, the electromagnetic force required for attracting the armature can be reduced, and the current required in the coil assembly 400 can be reduced. In addition, the invention can also reduce the current needed in the coil assembly by increasing the number of turns of the coil under the condition of outputting the same electromagnetic force.
In addition, the material of the integrated pressure housing component 100 of the invention is high-strength austenitic stainless steel, when the selected material is 06Cr18Ni11Nb, the basic allowable stress intensity of the material is 131MPa at 340 ℃, which is larger than the basic allowable stress intensity 111MPa of the material 022Cr19Ni10N in the prior art, the pressure housing between the coil component 400 and the hook component 200 can be made thinner, the minimum wall thickness can be reduced from 11.2mm to 9.4mm, thereby reducing the magnetic resistance of the austenitic stainless steel to the coil component 400, and reducing the required current in the coil component 400 under the condition of providing the same large electromagnetic force.
Through the mode, when the step length is adjusted to be 12mm, and the number of turns of the coil is increased by 40%, the current required by the lifting coil 303 can be reduced by 60%, so that the heat productivity of the coil assembly 400 is greatly reduced, cooling and ventilating equipment does not need to be added, and the reactor top structure is simplified.
In view of the above detailed description of the specific embodiments of the present invention, it can be seen that the nuclear power plant reactor control rod drive mechanism of the present invention has at least the following advantages over the prior art:
1) the pressure-resistant shell 100 is integrally arranged, no welding seam exists, the possibility of leakage of the reactor coolant can be reduced, in-service inspection is not required, and the operation and maintenance workload is reduced;
2) the pressure-resistant shell assembly 100 and the CRDM tube seat 700 are detachably connected through the threaded ring 102, the sealing ring 103 can realize self-tightening sealing by using medium pressure, the sealing is reliable, the structure is simple, the disassembly is convenient and quick, and the replacement time and the irradiated dose of maintenance personnel can be reduced;
3) the double-tooth claw 206 structure can improve the wear resistance of the claw and prolong the service life of the CRDM;
4) by optimizing the CRDM step length, increasing the number of turns of the coil, preparing the integrated pressure-resistant shell 100 by adopting the stabilized austenitic stainless steel 06Cr18Ni11Nb and using the thin-wall steel outer cover 600, the working current of the coil can be reduced, the heat productivity of the coil assembly 400 is reduced, the coil assembly 400 does not need ventilation cooling, the stack top structure is simplified, and the economy of the nuclear power station is improved;
5) by adopting the double-precision rod position detector assembly 500, the measurement precision and accuracy of rod position detection are effectively improved, the rod position detection range is expanded, the redundant design is added, the accurate control of the reactor power of the nuclear power station is facilitated, and the safe operation of the nuclear power station is ensured;
6) the hook component 200 is assembled and disassembled from the bottom of the pressure-resistant shell component 100, so that the risk of irradiation injury to operators can be reduced.
Appropriate changes and modifications to the embodiments described above will become apparent to those skilled in the art from the disclosure and teachings of the foregoing description. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (15)
1. The utility model provides a nuclear power station reactor control rod actuating mechanism, includes withstand voltage shell subassembly, hook component, drive rod subassembly, coil pack and stick position detector subassembly, its characterized in that: the pressure shell assembly is an integrated shell, the top of the pressure shell assembly is of a blind pipe structure, the bottom of the pressure shell assembly is detachably and hermetically mounted on a CRDM pipe seat of a top cover of the pressure vessel through a threaded ring, the threaded ring is screwed on the CRDM pipe seat through threads, the pressure shell assembly is tightly pressed on the CRDM pipe seat, and a sealing ring is arranged between the pressure shell assembly and the CRDM pipe seat.
2. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the sealing ring is a C-shaped sealing ring or an O-shaped sealing ring provided with a through hole.
3. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the sealing ring is made of nickel-based alloy, and the surface of the sealing ring is plated with silver.
4. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the sealing ring comprises an inner ring sealing ring and an outer ring sealing ring.
5. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the lower end of the hook component is supported on a CRDM tube seat of a top cover of the pressure vessel through a limiting nut.
6. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the hook component adopts a double-tooth hook.
7. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the coil assembly sleeve is established withstand voltage shell subassembly lower part, and it includes 3 solenoid, yoke, wiring and conduit, the hook subassembly corresponds and is equipped with iron core subassembly, and the iron core subassembly top-down that corresponds the setting on the solenoid of coil assembly and yoke and the hook subassembly forms promotion electro-magnet, removal electro-magnet and fixed electro-magnet.
8. The nuclear power plant reactor control rod drive mechanism of claim 7, wherein: the lifting electromagnet is provided with a lifting armature, and an air gap of the lifting armature is 11-15 mm.
9. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the upper part of the pressure-resistant shell component is provided with a step surface, the rod position detector component is supported on the step surface and comprises a positioning sleeve, an inner coil positioned in the positioning sleeve and close to the inner side, and an outer coil positioned in the positioning sleeve and close to the outer side.
10. The nuclear power plant reactor control rod drive mechanism of claim 9, wherein: the inner coil and the outer coil adopt a Gray code signal output form.
11. The nuclear power plant reactor control rod drive mechanism of claim 9, wherein: the inner coil and the outer coil are matched with each other.
12. The nuclear power plant reactor control rod drive mechanism of claim 9, wherein: the inner coil and the outer coil work independently.
13. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the pressure housing assembly is made of high strength austenitic stainless steel.
14. The nuclear power plant reactor control rod drive mechanism of claim 1, wherein: the sealing ring is a spring C-shaped sealing ring.
15. The nuclear power plant reactor control rod drive mechanism of any one of claims 1 to 14, wherein: and an outer cover is arranged on the outer side of the rod position detector assembly and supported on the coil assembly.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201711348475.XA CN107945890B (en) | 2017-12-15 | 2017-12-15 | Nuclear power station reactor control rod driving mechanism |
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| CN201711348475.XA CN107945890B (en) | 2017-12-15 | 2017-12-15 | Nuclear power station reactor control rod driving mechanism |
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| CN107945890A CN107945890A (en) | 2018-04-20 |
| CN107945890B true CN107945890B (en) | 2020-09-25 |
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| WO2019113927A1 (en) * | 2017-12-15 | 2019-06-20 | 中广核工程有限公司 | Nuclear power plant reactor control rod driving mechanism |
| CN108922637A (en) * | 2018-07-25 | 2018-11-30 | 中广核研究院有限公司 | A kind of nuclear power station-service control rod drive mechanism |
| CN109378092A (en) * | 2018-11-12 | 2019-02-22 | 中国原子能科学研究院 | A kind of pool low temperature heap control rod drive mechanism electromagnet apparatus |
| CN109830310A (en) * | 2019-01-11 | 2019-05-31 | 中广核工程有限公司 | Ship reactor improved electric magnetic-type control rod drive mechanism |
| CN109994224A (en) * | 2019-01-11 | 2019-07-09 | 中广核工程有限公司 | Ship reactor control rod drive mechanism |
| JP2022523534A (en) * | 2019-02-28 | 2022-04-25 | ウェスティングハウス エレクトリック カンパニー エルエルシー | Control rod drive mechanism diagnostic tool using voltage and current recording |
| CN109920569B (en) * | 2019-03-15 | 2020-10-13 | 中广核核电运营有限公司 | Addressing device and method for nuclear power station reactor control rods |
| CN112509717B (en) * | 2020-11-27 | 2023-05-02 | 中广核检测技术有限公司 | Source guiding pipe lifting device for in-service inspection of claw gaskets of control rod driving mechanism |
| CN112863705B (en) * | 2020-12-28 | 2022-11-25 | 中国原子能科学研究院 | Pressure boundary sealing system of control rod driving mechanism |
| CN114188052A (en) * | 2021-10-20 | 2022-03-15 | 中广核核电运营有限公司 | Portable transfer device for sealing ring of reactor pressure vessel of nuclear power station |
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