CN205722806U - A kind of floating type reactor control rod driving mechanism - Google Patents

A kind of floating type reactor control rod driving mechanism Download PDF

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Publication number
CN205722806U
CN205722806U CN201620406680.1U CN201620406680U CN205722806U CN 205722806 U CN205722806 U CN 205722806U CN 201620406680 U CN201620406680 U CN 201620406680U CN 205722806 U CN205722806 U CN 205722806U
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Prior art keywords
screw
floating type
type reactor
control rod
driving mechanism
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白勇军
刘刚
史骁辰
王丰
林绍萱
王德斌
翁娜
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Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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    • 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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Abstract

This utility model provides the CRDM of a kind of floating type reactor, including pressure-bearing shell parts, drives motor component, scram release mechanism components, magnetic inversion line coil component and drives screw part.The floating type reactor control rod driving mechanism that this utility model provides, its mechanism driving reliable in action, running precision is high, simple for structure, can realize the function that the power under the various operating mode of floating type reactor controls and reactor safety controls.

Description

A kind of floating type reactor control rod driving mechanism
Technical field
This utility model relates to the CRDM of nuclear power plant reactor, specifically one and is applied to float The CRDM of formula reactor.
Background technology
Command bundle rods for nuclear reactors drive mechanism is watching of the most important control system of reactor and safety system Take equipment, be responsible for the startup of reactor, power adjustments, shutdown and safety (promptly) shutdown etc. and produce fortune Row and safety control function.Owing to working environment is different from continental rise, the floating type power station reactor moment is in week In phase property swinging condition, now drive mechanism can not remain fixing vertical state, relies on gravity as control System rod inserts the driving force of reactor core can not application solutions scram action.When floating heap generation wide-angle tilt, When even toppling, gravity just becomes the resistance of control rod motion, hinders its former setting scram action.Cause This, the driving working mechanism of original continental rise command bundle rods for nuclear reactors drive mechanism can not meet floating reaction The production and safety assurance function of heap.For ensureing that floating type reactor the most normally works, its control Rod drive mechanism processed must use novel actuation techniques and motion credibility safeguard.
In the design of floating type reactor control rod driving mechanism is applied, Russia is moved because having substantial amounts of core Power ice breaker and abundant developing operation floating type reactor practical experience, thus become the leading of this field Sheep.ABV, VBER and KLT series of Russia's test machines designing for manufacturing office (OKBM) is floating type Reactor is its years of researches achievement.Wherein KLT-40 series is the floating type nuclear reactor that it is the most ripe, This reactor provides power for nuclear-powered icebreaker the northern most evil bad environmental work of Russia, and it always runs Time is more than 7000 heap years.Akademik Lomonosov is nuclear power group of Russia (Rosenergoatom) The global First floating nuclear power plant of design, is equipped with 2 35MWe (KLT-40S) reactors, power station Being predefined in trail run in 2016, the external CRDM that it uses uses motor and gear teeth Bar drive mechanism [KLT-40floating nuclear heat and power unit with KLT-40s reactor plant (OKBM,Russian Federation).In:Status of advanced light water reactor designs IAEA-TECDOC-1391.Vienna:International Atomic Energy Agency,IAEA,2004: 733-754.].This pinion and-rack drive mechanism reliable in action, but because of drive mechanism feature, take up room Volume is excessive, it is impossible to adapt to high-density arrangement demand.The atomic energy research establishment (JAERI) of Japan is then endeavoured In built-in ball nut screw type CRDM research and development [Ishida, Toshihisa.Imayoshi, Shou.et al.Development of in-vessel type control rod drive mechanism for marine Reactor.Journal of Nuclear Science and Technology.2001,38 (7), 557 570.], and will It is applied to marine integral reactor MRX, DRX.This employing leading screw roller nut type drive mechanism During design, discerptible roller nut defines complicated connection with driving screw, and this may be in the properly functioning phase Between have influence on control rod kinematic accuracy.The emergency shut-down release of driving screw is it is also possible to screw thread or guide screw simultaneously Bar structural intergrity causes the damage of unrepairable.When there is scram event, nut is the most de-with driving screw From.As again recovered to connect, it will introducing the deviation of relative position, this will cause roller nut and driving screw Again the difficulty engaged improves, contact situation becomes more sophisticated.Additionally, for complicated detachable roller For nut, the abrasion elapsing generation over time can would is that an inevitable problem.
Utility model content
This utility model, for the deficiencies in the prior art, proposes a kind of floating type reactor control rod and drives machine Structure.
Floating type reactor control rod driving mechanism includes:
Pressure-bearing shell parts;Described pressure-bearing shell parts are by screw stroke housing, motor pressure-bearing shell and lead Form to sleeve pipe;Described screw stroke housing, motor pressure-bearing shell and guide thimble collectively form pressure boundary; Wherein said motor pressure-bearing shell is connected fixing with reactor lid;
Drive motor component;Described driving motor component is by stator winding, rotor, nut and bearing structure Becoming, wherein stator winding is arranged on the outside or inside of described motor pressure-bearing shell;Described rotor and nut are even Integral, and be contained in described motor pressure-bearing shell by described bearing holder (housing, cover);Described stator winding is because of curent change And produce alternating magnetic field, described rotor is produced torque, drives described nut rotation thus lead-screw Linear motion;
Scram release mechanism components;Described scram release mechanism components is by scram spring, release spring, hook Pawl, connecting rod, armature form;Described scram spring, release spring, hook, connecting rod, armature are sleeved on institute State in guide pad;
Drive screw part;Described driving screw part includes screw rod and the core bar of hollow;Described core bar is positioned at Described inside screw is freely slidable, and described screw flight section engages with nut, one end of described screw rod with Guide pad connects, and the other end enters inside screw offer guide effect, one end of described core bar for installing core bar Be connected with C&P systems, the other end be connected with hook and with described scram spring contact;
Magnetic inversion line coil component;Described magnetic inversion line coil component is made up of multiple yoke assemblies and multiple actuating coil, And it is centered around described screw stroke hull outside.
Preferably, described hook, connecting rod and armature constitute a linkage rod slide block mechanism, by described armature Move up and down and control the folding and unfolding action of described hook.
Preferably, can use between described guide pad with described driving screw part and threaded.
Preferably, there is flow-guiding channel the inside of described guide pad, to reduce fluid resistance.
Preferably, between described guide pad and described screw stroke housing, use the convex-concave groove way of contact, in case The only rotation of described guide pad.
Preferably, described armature moves up and down and is jointly cooperated reality by described magnetic inversion line coil component and release spring Existing, after described magnetic inversion line coil component is energized, produce magnetic field force, described armature adhesive;After power-off, magnetic field force disappears Losing, described release spring flicks described armature.
Compared with prior art, this utility model has the advantages that
1, the floating type reactor control rod driving mechanism that this utility model provides, its mechanism driving action can Leaning on, running precision is high, simple for structure, can realize the power control under the various operating mode of floating type reactor The function that system and reactor safety control.
2, the floating type reactor control rod driving mechanism that this utility model provides, is positioned over reactor pressure and holds Outside device top cover, can effectively reduce motor driving part part temperature by the design of structure heat shielding and outside cooling Degree, is conducive to ensureing electric component steady operation.
3, the floating type reactor control rod driving mechanism that this utility model provides, uses integral nut to rotate and drives Dynamic screw rod moves along a straight line, and nut and screw rod remain engagement, will not send out because of emergent rod drop or reload Raw disengaging, thus without producing by again engaging the site error problem connected and produce, it is ensured that the accuracy of mesh And transmission stability, improve the wearability of drive disk assembly, reliability and service life.
4, the floating type reactor control rod driving mechanism that this utility model provides, screw rod upper end uses and guides Block assembly limits the rotation of screw rod, ensures the axis coaxle degree of screw rod and nut simultaneously, it is to avoid ridge occurs Kill phenomenon.
5, the floating type reactor control rod driving mechanism that this utility model provides, inside screw hollow, equipped with Core bar is connected with C&P systems.When emergent rod drop, core bar is quickly ejected by scram spring, promotes and controls Rod assembly inserts reactor core.Owing to there is no screw rod with scram action, reduce the impact to reactor core, protect simultaneously Protect the integrity of screw flight.
6, the floating type reactor control rod driving mechanism that this utility model provides, uses and is compressed in guide pad The scram spring in portion is as accumulation of energy assembly, it is possible to achieve arbitrarily operating mode, the in emergency circumstances safety of any attitude Scram.This spring is in compressive state all the time simultaneously, will not cause spring-compressed because of control rod change in location Height change, does not therefore have alternate stress and the fatigue rupture that produces.
Accompanying drawing explanation
Fig. 1 is that the floating type reactor control rod driving mechanism work meeting this utility model preferred embodiment is shown It is intended to.
Fig. 2 is the guide pad meeting this utility model preferred embodiment and screw stroke housing functional contact situation Cross sectional representation.
Fig. 3 is scram release mechanism components schematic diagram under the scram operating mode meeting this utility model preferred embodiment.
Detailed description of the invention
Understandable for enabling above-mentioned purpose of the present utility model, feature and advantage to become apparent from, below in conjunction with attached This utility model is described in further detail by figure and detailed description of the invention.
As shown in Figure 1, floating type reactor control rod driving mechanism of the present utility model includes pressure-bearing shell Parts, driving motor component, scram release mechanism components, magnetic inversion line coil component and driving screw part.Its In: pressure-bearing shell parts are made up of screw stroke housing 11, motor pressure-bearing shell 17 and guide thimble 18, Collectively forming pressure boundary, wherein motor pressure-bearing shell 17 is connected solid with reactor lid (not marking in figure) Fixed;Drive motor component by stator winding 15, rotor 14, nut 13, thrust bearing 16 and journal bearing 12 are constituted, and wherein stator winding 15 may be installed the outside or inside of motor pressure-bearing shell 17 (this legend is Outside), rotor 14 and nut 13 are connected, and are sleeved on electricity by thrust bearing 16 and journal bearing 12 In machine pressure-bearing shell 17;Scram release mechanism components is by scram spring 4, release spring 5, hook 6, connecting rod 7, armature 8 forms and is sleeved in guide pad 3, and wherein hook 6, connecting rod 7 and armature 8 constitute a company Bar slide block mechanism, controls the folding and unfolding action of hook 6 by the up and down motion of armature 8;Armature about 8 is transported Dynamic jointly cooperated realizations by actuating coil 2 and release spring 5, generation magnetic field force after actuating coil 2 is energized, Armature 8 adhesive;After power-off, magnetic field force disappears, and release spring 5 flicks armature 8;Guide pad 3 and screw rod 10 Between can use threaded, have flow-guiding channel inside it, to reduce fluid resistance;Magnetic inversion line coil component by Multiple yoke assemblies 1 and multiple actuating coil 2 form, and it is outside to be centered around screw stroke housing 11;Drive Screw part includes screw rod 10 and the core bar 9 of hollow, and core bar 9 is positioned at screw rod 10 inside and can axially free slide, Wherein the thread segment of screw rod 10 engages with nut 13, and one end of screw rod 10 is connected with guide pad 3, the other end Screw rod 10 internal offer guide effect, one end of core bar 9 and C&P systems (figure is entered for installing core bar 9 In do not mark) connect, the other end connects with hook 6 and contacts with scram spring 4.
It is the working condition of CRDM, now actuating coil 2 under nominal situation shown in accompanying drawing 1 Remaining "on" position, the magnetic field force produced after energising makes armature 8 adhesive, armature 8 be pushed away by connecting rod 7 Dynamic hook 6 keeps the action of grasping core bar 9.When reactor regulation system sends control rod movement instruction, Produce alternating magnetic field by the alternating current controlled within stator winding 15, rotor 14 is produced torque, with Step drives nut 13 to rotate, thus drives the screw rod 10 engaged with nut 13 to move along a straight line.
As in figure 2 it is shown, the biography that nut 13 rotates, screw rod 10 moves along a straight line used at this utility model In flowing mode, the motion that on the one hand screw stroke housing 11 is screw rod 10 provides guide effect, on the other hand For preventing screw rod 10 from rotation occurring, adopt between the guide pad 3 and the screw stroke housing 11 that are connected with screw rod 10 With the convex-concave groove way of contact.
As it is shown on figure 3, when there is emergency safety situation power-off, drive motor component to lose efficacy, screw rod 10 nothing Method is moved.Now actuating coil 2 makes magnetic field force disappear due to power-off, and release spring 5 flicks armature 8, rank Ferrum 8 promotes hook 6 to open by connecting rod 7, and core bar 9 quickly promotes control under the effect of scram spring 4 Rod assembly enters reactor core.
Compared with prior art, the present embodiment has the advantages that
1. the floating type reactor control rod driving mechanism that the present embodiment provides, its mechanism driving reliable in action, fortune Row degree of accuracy is high, simple for structure, can realize the power control under the various operating mode of floating type reactor The function that system and reactor safety control.
2. the floating type reactor control rod driving mechanism that the present embodiment provides, is positioned over reactor pressure vessel top Lid is outside, can effectively reduce motor driving part part temperature by the design of structure heat shielding and outside cooling Degree, is conducive to ensureing electric component steady operation.
3. the floating type reactor control rod driving mechanism that the present embodiment provides, uses integral nut to rotate and drives spiral shell Bar moves along a straight line, and nut and screw rod remain engagement, will not be because of emergent rod drop or reload Depart from, thus without producing by again engaging the site error problem connected and produce, it is ensured that The accuracy of mesh and transmission stability, improve the wearability of drive disk assembly, reliability and service life.
4. the floating type reactor control rod driving mechanism that the present embodiment provides, screw rod upper end uses guiding packaged Put the rotation limiting screw rod, ensure the axis coaxle degree of screw rod and nut simultaneously, it is to avoid screw thread occurs Tooth kills phenomenon.
5. the floating type reactor control rod driving mechanism that the present embodiment provides, inside screw hollow, equipped with core bar It is connected with C&P systems.When emergent rod drop, core bar is quickly ejected by scram spring, promotes control Rod assembly processed inserts reactor core.Owing to there is no screw rod with scram action, reduce the impact to reactor core, Protect the integrity of screw flight simultaneously.
6. the floating type reactor control rod driving mechanism that the present embodiment provides, uses and is compressed within guide pad Scram spring is as accumulation of energy assembly, it is possible to achieve arbitrarily operating mode, the in emergency circumstances peace of any attitude Full scram.This spring is in compressive state all the time simultaneously, will not cause because of control rod change in location Compressed height of spring changes, and does not therefore have an alternate stress and the fatigue rupture that produces.
In this specification, each embodiment uses the mode gone forward one by one to describe, and what each embodiment stressed is With the difference of other embodiments, between each embodiment, identical similar portion sees mutually.For For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so the comparison described is simple Single, relevant part sees method part and illustrates.
Each specifically should being used for can be used different methods to realize described merit by those skilled in the art Can, but this realization is it is not considered that exceed scope of the present utility model.
Obviously, those skilled in the art can carry out various change and modification without deviating from this to utility model The spirit and scope of utility model.So, if these amendments of the present utility model and modification belong to this practicality Within the scope of novel claim and equivalent technologies thereof, then this utility model be also intended to include these change and Including modification.

Claims (6)

1. a floating type reactor control rod driving mechanism, it is characterised in that including:
Pressure-bearing shell parts;Described pressure-bearing shell parts are by screw stroke housing, motor pressure-bearing shell and lead Form to sleeve pipe;Described screw stroke housing, motor pressure-bearing shell and guide thimble collectively form pressure boundary; Wherein said motor pressure-bearing shell is connected fixing with reactor lid;
Drive motor component;Described driving motor component is by stator winding, rotor, nut and bearing structure Becoming, wherein stator winding is arranged on the outside or inside of described motor pressure-bearing shell;Described rotor and nut are even Integral, and be contained in described motor pressure-bearing shell by described bearing holder (housing, cover);Described stator winding is because of curent change And produce alternating magnetic field, described rotor is produced torque, drives described nut rotation thus lead-screw Linear motion;
Scram release mechanism components;Described scram release mechanism components is by scram spring, release spring, hook Pawl, connecting rod, armature form;Described scram spring, release spring, hook, connecting rod, armature are sleeved on institute State in guide pad;
Drive screw part;Described driving screw part includes screw rod and the core bar of hollow;Described core bar is positioned at Described inside screw is freely slidable, and described screw flight section engages with nut, one end of described screw rod with Guide pad connects, and the other end enters inside screw offer guide effect, one end of described core bar for installing core bar Be connected with C&P systems, the other end be connected with hook and with described scram spring contact;
Magnetic inversion line coil component;Described magnetic inversion line coil component is made up of multiple yoke assemblies and multiple actuating coil, And it is centered around described screw stroke hull outside.
Floating type reactor control rod driving mechanism the most as claimed in claim 1, it is characterised in that described Hook, connecting rod and armature constitute a linkage rod slide block mechanism, control institute by the up and down motion of described armature State the folding and unfolding action of hook.
Floating type reactor control rod driving mechanism the most as claimed in claim 1, it is characterised in that described Can use between guide pad with described driving screw part and threaded.
Floating type reactor control rod driving mechanism the most as claimed in claim 1, it is characterised in that described There is flow-guiding channel the inside of guide pad, to reduce fluid resistance.
Floating type reactor control rod driving mechanism the most as claimed in claim 1, it is characterised in that described The convex-concave groove way of contact is used, to prevent turning of described guide pad between guide pad and described screw stroke housing Dynamic.
Floating type reactor control rod driving mechanism the most as claimed in claim 1, it is characterised in that described Armature moves up and down and is jointly cooperated realization, when described yoke coil by described magnetic inversion line coil component and release spring Magnetic field force, described armature adhesive is produced after parts energising;After power-off, magnetic field force disappears, described release spring bullet Open described armature.
CN201620406680.1U 2016-05-06 2016-05-06 A kind of floating type reactor control rod driving mechanism Active CN205722806U (en)

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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105788667A (en) * 2016-05-06 2016-07-20 上海核工程研究设计院 Control rod driving mechanism of floating type reactor
CN107924721A (en) * 2015-07-29 2018-04-17 原子能技术公司 The nuclear reactor of bolt and nut driving with reactor core reaction controlling component
WO2024066488A1 (en) * 2022-09-27 2024-04-04 上海核工程研究设计院股份有限公司 Motor lead screw type control rod driving mechanism and driving method thereof

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107924721A (en) * 2015-07-29 2018-04-17 原子能技术公司 The nuclear reactor of bolt and nut driving with reactor core reaction controlling component
CN107924721B (en) * 2015-07-29 2020-03-10 原子能技术公司 Screw-nut driven nuclear reactor with core reaction control member
CN105788667A (en) * 2016-05-06 2016-07-20 上海核工程研究设计院 Control rod driving mechanism of floating type reactor
WO2024066488A1 (en) * 2022-09-27 2024-04-04 上海核工程研究设计院股份有限公司 Motor lead screw type control rod driving mechanism and driving method thereof

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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.

Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE