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CA3155316C - Moveable isolated rod couplings for use in a nuclear reactor control rod drive - Google Patents

Moveable isolated rod couplings for use in a nuclear reactor control rod drive Download PDF

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Publication number
CA3155316C
CA3155316C CA3155316A CA3155316A CA3155316C CA 3155316 C CA3155316 C CA 3155316C CA 3155316 A CA3155316 A CA 3155316A CA 3155316 A CA3155316 A CA 3155316A CA 3155316 C CA3155316 C CA 3155316C
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Canada
Prior art keywords
overtravel
isolation barrier
control rod
control
control element
Prior art date
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Application number
CA3155316A
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French (fr)
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CA3155316A1 (en
Inventor
Kenneth Allan MORGAN
David Lee MAJOR
Randy Morris BROWN
Gerald Alan DEAVER
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.)
GE Hitachi Nuclear Energy Americas LLC
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GE Hitachi Nuclear Energy Americas LLC
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
Priority claimed from US15/644,908 external-priority patent/US10872703B2/en
Application filed by GE Hitachi Nuclear Energy Americas LLC filed Critical GE Hitachi Nuclear Energy Americas LLC
Publication of CA3155316A1 publication Critical patent/CA3155316A1/en
Application granted granted Critical
Publication of CA3155316C publication Critical patent/CA3155316C/en
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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control 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
    • G21C7/12Means for moving control elements to desired position
    • G21C7/14Mechanical drive arrangements
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Surgical Instruments (AREA)
  • Transmission Devices (AREA)

Abstract

Control rod drives include linearly-moveable control elements inside an isolation barrier. Control rod drives move the control element through secured magnetic elements subject to magnetic fields. Induction coils may generate magnetic fields and be moveable across a full stroke length of the control element in the reactor. A motor may spin a linear screw to move the induction coils on a vertical travel nut. A control rod assembly may house the magnetic elements and directly, removably join to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier may release the latches to leave the overtravel position. Operation includes moving the induction coils with a linear screw to drive the control element to desired insertion points, including full insertion by gravity following de-energization. No direct connection may penetrate the isolation barrier.

Description

MOVEABLE ISOLATED ROD COUPLINGS FOR USE IN A NUCLEAR REACTOR
CONTROL ROD DRIVE
[0001] This application is a division of application number CA 3,029,845, filed July 13, 2017.
BRIEF DESCRIPTIONS OF THE DRAWINGS
[0002] Example embodiments may become more apparent by describing, in detail, the attached drawings, wherein like elements are represented by like reference numerals, which are given by way of illustration only and thus do not limit the terms which they depict.
[0003] FIG. 1 is an illustration of a drive rod connection to a control rod assembly useable in example embodiments.
[0004] FIG. 2 is a plan illustration of an example embodiment control rod drive mechanism using extended lift coils.
[0005] FIG. 3 is a profile illustration of the example embodiment control rod drive mechanism using extended lift coils.
[0006] FIG. 4 is another profile illustration of the example embodiment control rod drive mechanism using extended lift coils.
BACKGROUND
[0007] FIG. 1 is an illustration of a drive rod¨control rod assembly (CRA) connection 10 useable with example embodiment control drives. In most conventional PWR
control rod assemblies, drive rod 11 and actuating rod 12 extend in lateral support tube 16 from above a reactor pressure vessel 1 down to a lockable spud or bayonet 13 that joins to CRA 15 via locking plug 14. CRA 15 contains neutron absorbent materials what can be used to control a nuclear chain reaction based on an amount of vertical insertion. Control rods are driven from above by vertical movement of actuating rod 12 and drive rod 11, under force from the control rod drive mechanism.

Date Recue/Date Received 2022-04-13
[0008] The following documents describe control rod drive mechanisms used in nuclear reactors: US Pat Pub 2015/0255178 to Tsuchiya et al; US Pat 4423002 to Wiart et al.; US Pat 4369161 to Martin; US Pat 4338159 to Martin et al.; US Pat 4044622 to Matthews; US Pat 9305669 to Hyde et al.; US Pat 3933581 to McKeehan et al.; US Pat 4048010 to Eschenfelder et al.; US Pat 4092213 to Nishimura; US Pat 4147589 to Roman et al.; US Pat 4288898 to Adcock;
US Pat 4484093 to Smith; US Pat 5276719 to Batheja; US Pat 8915161 to Akatsuka et al.; US
Pat 4518559 to Fischer et al.; US Pat 5517536 to Goldberg et al.; US Pat 5428873 to Hitchcock et al.; US Pat 8571162 to Maruyama et al.; US Pat 8757065 to Fjerstad et al.;
US Pat 5778034 to Tani; US Pat 9336910 to Shargots et al.; US Pat 3941653 to Thorp, II; US Pat 3992255 to DeWesse; US Pat 8811562 to DeSantis; and "In-vessel Type Control Rod Drive Mechanism Using Magnetic Force Latching for a Very Small Reactor" Yoritsune et al., J.
Nuc. Sci. & Tech., Vol. 39, No. 8, p. 913-922 (Aug. 2002).
SUMMARY
[0009] Example embodiments include control rod drives including linearly-moveable control elements to control neutronics in a nuclear reactor. Example control rod drives may include an isolation barrier impermeably separating pressurized reactor internals from external spaces like containment. One or more induction coils are linearly moveable outside of the isolation barrier, while the control element is inside the isolation barrier in the reactor.
Example control rod drives may move the control element via a magnet immovably connected to the same by linearly moving the induction coils to linearly drive the magnets. The induction coils may be mounted on a vertical travelling nut and linear screw to fully move across a whole distance equivalent to complete insert and withdrawal of the control element from the reactor. A
closed coolant loop may cool the induction coils, which may otherwise be maintained in a vacuum or other environment distinct from reactor internals in a housing about an end of the reactor. Example embodiment control rod drives may include a control rod assembly housing the magnet that directly joins to the control element. The control rod assembly may lock with magnetic overtravel latches inside the isolation barrier to maintain an overtravel position. Overtravel release coils outside the isolation barrier can release or otherwise move the latches, which may be spring-biased, to adjust the connection between the latches and assembly.

Date Recue/Date Received 2022-04-13 [00101 Example methods include linearly moving the induction coil to drive the control element via the magnetic material secured to the same. In this way, the control element may be inserted and withdrawn with no mechanical linkage permeating the isolation barrier. By mounting the induction coil on a vertical travelling nut that moves linearly with rotation of a linear screw, the magnetic material may be driven with the moving induction coil, thus driving the control element. A motor can rotate the linear screw outside the isolation barrier to achieve this motion. When the coil is de-energized, the control element may be driven by gravity into a reactor, achieving a scram. Example methods may drive the control rod to an overtravel position, where overtravel latches hold the same, for removal, attachment, and/or other maintenance of the control element from/to/on the control rod assembly. Following desired overtravel actions, the overtravel coils may be energized to release the latches through magnetic materials in the latch biasing them to an open position.
DETAILED DESCRIPTION
[00111 Because this is a patent document, general broad rules of construction should be applied when reading it. Everything described and shown in this document is an example of subject matter falling within the scope of the claims, appended below. Any specific structural and functional details disclosed herein are merely for purposes of describing how to make and use examples. Several different embodiments and methods not specifically disclosed herein may fall within the claim scope; as such, the claims may be embodied in many alternate forms and should not be construed as limited to only examples set forth herein.
[0012] It may be understood that, although the terms first, second, etc.
may be used herein to describe various elements, these elements should not be limited to any order by these terms.
These terms are used only to distinguish one element from another; where there are "second" or higher ordinals, there merely must be that many number of elements, without necessarily any difference or other relationship. For example, a first element could be termed a second element, and, similarly, a second element could be termed a first element, without departing from the scope of example embodiments or methods. As used herein, the term "and/or"
includes all combinations of one or more of the associated listed items. The use of "etc."
is defined as "et Date Recue/Date Received 2022-04-13 cetera" and indicates the inclusion of all other elements belonging to the same group of the preceding items, in any "and/or" combination(s).
[0013] It may be understood that when an element is referred to as being "connected,"
"coupled," "mated," "attached," "fixed," etc. to another element, it can be directly connected to the other element, or intervening elements may be present. In contrast, when an element is referred to as being "directly connected," "directly coupled," etc. to another element, there are no intervening elements present. Other words used to describe the relationship between elements should be interpreted in a like fashion (e.g., "between" versus "directly between," "adjacent"
versus "directly adjacent," etc.). Similarly, a term such as "communicatively connected" includes all variations of information exchange and routing between two electronic devices, including intermediary devices, networks, etc., connected wirelessly or not.
[0014] As used herein, the singular forms "a," "an," and "the" are intended to include both the singular and plural forms, unless the language explicitly indicates otherwise. It may be further understood that the terms "comprises," "comprising," "includes,"
and/or "including,"
when used herein, specify the presence of stated features, characteristics, steps, operations, elements, and/or components, but do not themselves preclude the presence or addition of one or more other features, characteristics, steps, operations, elements, components, and/or groups thereof [0015] The structures and operations discussed below may occur out of the order described and/or noted in the figures. For example, two operations and/or figures shown in succession may in fact be executed concurrently or may sometimes be executed in the reverse order, depending upon the functionality/acts involved. Similarly, individual operations within example methods described below may be executed repetitively, individually or sequentially, to provide looping or other series of operations aside from single operations described below. It should be presumed that any embodiment or method having features and functionality described below, in any workable combination, falls within the scope of example embodiments.
[0016] The Inventors have newly recognized that control rod drives in nuclear reactors are typically mechanical drives using direct contact points that must pass through or be inside a reactor CRDM pressure boundary 150. Such direct contact and positioning creates a challenging environment for the mechanical drives that typically must operate to move control rods over a period of several months or years without maintenance. For example, reactor temperatures, leaked coolant, and noncondensible gasses found inside example embodiment CRDM

Date Recue/Date Received 2022-04-13 pressure boundary 150 can cause corrosion and associated stress corrosion cracking, hydriding, and hydrogen deflagration problems with mechanical drive parts. The cooling mechanisms and heat from direct contact with the drives interact with example embodiment CRDM
200 pressure boundary 150 to also cause thermal cycling problems during actuation of mechanical drives over the course of operation. Penetrations in a control rod drive required for mechanical connection also represent an avenue for leakage of reactor coolant. The Inventors have newly recognized a need for a control rod drive that has less engagement with example embodiment pressure boundary 150 as well as mechanical contacts that represent high-failure points.
Example embodiments described below uniquely enable solutions to these and other problems discovered by the Inventors.
Positioning and Scramming the CRDM
[0017] FIG. 2 is a plan view illustration of an example embodiment control rod drive mechanism 200. FIGS. 3 and 4 are profile views of the same example embodiment control rod drive mechanism 200 of FIG. 2, with FIG. 3 showing assembly 210 in a seated position and FIG.
4 showing assembly 210 in an overtravel position. Descriptions of actuating rod 103, position indication magnet 115, lift rod actuating magnet 104, key features 118, are given in the co-owned U.S. patent application 15/640,428 (publication number US 20180019026) filed June 30, 2017 to Morgan et al. for "STATIONARY ISOLATED ROD COUPLINGS FOR USE IN A
NUCLEAR REACTOR CONTROL ROD DRIVE".
[0018] As seen in FIG. 4, following coupling of lift rod 112 and drive rod 111 to CRA 210, CRA 210 is positioned by outer linear screw 123 and scram lift coils.
Levitating and scram coils 124 are mounted on outer vertical travel nut 125 and are energized to magnetically couple lift rod 112 via lift magnet 114 or other materials within example embodiment pressure boundary 150. CRDM Motor 126 rotates outer linear screw 123 within CRDM
structural housing 106. Rotation of outer linear screw 123 causes vertical movement of outer vertical travel nut 125 and levitating and scram coils 124 that are keyed to prevent rotation by position indication probe housing 135. Outer vertical travel nut 125 and energized levitating and scram coils 124 are moved vertically on outer linear screw 123 within the drive range. Levitated lift rod 112, drive rod 111, and CRA 210 follow the magnetic field. Feedback from position sensors and position indication probes 105 control outer linear screw 123 rotation and move Date Recue/Date Received 2022-04-13 CRA 210 in CRDM 200 to its desired position for reactor control. Outer linear screw 123 provides fine motion control of internal lift rod 112, drive rod 111 and CRA
210.
[0019] There is a vacuum 121 between example embodiment CRDM 200 pressure boundary 150 and outer linear screw 123 and between levitating and scram coils 124 and outer linear screw 123 to limit heat transfer between coils 124 and CRDM pressure boundary 150. Vacuum 121 may provide a more uniform temperature gradient on example embodiment CRDM

pressure boundary 150 that minimizes thermal cycling.
[0020] Simplification of example embodiment CRDM 200 pressure boundary 150 and lift rod internals may allow the size of CRDM pressure boundary 150 to be reduced such that example embodiment CRDM 200 pressure boundary 150 wall thickness can be enhanced to minimize effects of corrosion, hydriding, and hydrogen deflagration problems.
[00211 Reactor safety features requiring a scram provide inputs to the control system for levitating and scram coils 124 (in their energized state). If reactor conditions warrant a scram, the control system de-energizes levitating and scram coils 124. This drops the magnetic field levitating lift rod 112, drive rod 111, and CRA 210, and gravity quickly acts on the unsupported weight to scram the reactor. Any CRDM failure causing a loss of scram coil current may also lead to a conservative control rod scram.
[0022] Levitating and scram coils 124 are continuously energized during CRDM operation and may use a cooling flow through their travel range. Flexible coolant inlet/outlet lines 107 (FIG. 5) are oriented from the top of CRDM 200 and reach levitating and scram coils 124 through slotted openings of CRDM structural housing 106. Coolant inlet/outlet lines 107 along with the control circuits for levitating and scram coil 124 can have counter weights or spring reel feeds to keep them under slight tension during drive operation.
CRDM preparation for Refueling Process [0023] Drive rod 111 may be decoupled from CRA 210 as described in the above-mentioned co-owned U.S. patent application (publication number US
20180019026). Outer linear screw 123, vertical travelling nut 125, and energized levitating and scram coils 124 are then used to maneuver lift rod 112 and drive rod 111 to an overtravel position as shown in FIG. 3. In the overtravel position, two spring-actuated overtravel latches 116 engage a shoulder or window in example embodiment CRDM 200 pressure boundary 150 to Date Recue/Date Received 2022-04-13 lock CRA 210 at the overtravel height. Power can then be secured to or disconnected from motor 126 (FIG. 2) and levitating and scram coils 124 (FIGS. 2 & 4) for duration of the refueling process. The lower end of drive rod 111 is carried to an elevation that is clear of the upper to lower vessel disassembly process.
[0024] When refueling is completed, motor 126, outer linear screw 123, and levitating and scram coil 124 are energized to carry the weight of lift rod 112 and drive rod 111 in the overtravel position. Overtravel release coils 108 are then energized to compress spring actuated structural support 117 resting on example embodiment CRDM 200 pressure boundary 150 structural support. Magnetic material 119 drawn outward on overtravel latches 116 causes the spring actuated structural support 117 to clear example embodiment CRDM 200 pressure boundary 150 structural support and the drive can be positioned to recouple to CRA 210 for operation.
CRDM support Structure [0025] As shown in FIG. 2, CRDM pressure boundary 150 is supported vertically off of the CRDM nozzle pressure boundary flange 120 in CRDM structural housing 106 of the RPV
flange. Lateral support to upper portions of CRDM pressure boundary 150 is not provided other than the close proximity of linear screw 123 across vacuum gap 121.
[0026] CRDM structural housing 106 is also fixed to CRDM nozzle pressure boundary flange 120. Insulating washers and other items can be utilized to reduce the thermal heat transfer from the RPV head to components in CRDM 200. The internal bearings/bushings of rotating linear screw 123 are supported from CRDM structural housing 106 and not pressure boundary 150 to avoid heat conduction. PIP probes 105 are inserted vertically through the upper flange of CRDM structural housing 106 and are laterally supported at a minimum of the upper and lower ends of CRDM structural housing 106. Motor 126, brake, and position sensors may be mounted on the top end of CRDM structural housing 106 and engage outer linear screw 123 through a geared coupling. Cooling lines 107 are run to motor 126 which is located as remote as possible from the reactors thermal and radiation output. Motor 126 may also be isolated by a vacuum 121 from CRDM pressure boundary 150.
[0027] Example embodiments and methods thus being described, it may be appreciated by one skilled in the art that example embodiments may be varied and substituted through routine Date Recue/Date Received 2022-04-13 experimentation while still falling within the scope of the following claims.
For example, a generally vertical orientation with control rod drives above a pressure vessel is shown in connection with some examples; however, other configurations and locations of control rods and control rod drives, are compatible with example embodiments and methods simply through proper dimensioning and placement - and fall within the scope of the claims.
Such variations are not to be regarded as departure from the scope of these claims.

Date Recue/Date Received 2022-04-13

Claims (2)

WHAT IS CLAIMED IS:
1. A control rod drive for positioning a control element in a nuclear reactor, the drive comprising:
an isolation barrier;
a moveable induction coil outside of the isolation barrier;
a magnetic material inside the isolation barrier, wherein the material is configured to secure to the control element, and wherein the isolation barrier is impermeable to gasses and fluids such that a pressure gradient is maintained across the inside and the outside of the isolation barrier;
a plurality of magnetic overtravel latches inside the isolation barrier configured to hold the control element in an overtravel position; and a plurality of overtravel release coils outside the isolation barrier configured to move the overtravel latches into a release position.
2. The control rod drive of claim 1, wherein each of the magnetic overtravel latches includes a spring biasing the overtravel latch into a holding position, and wherein the overtravel release coils are configured to bias compress the spring through magnetic force.

Date Recue/Date Received 2022-04-13
CA3155316A 2016-07-13 2017-07-13 Moveable isolated rod couplings for use in a nuclear reactor control rod drive Active CA3155316C (en)

Applications Claiming Priority (5)

Application Number Priority Date Filing Date Title
US201662361628P 2016-07-13 2016-07-13
US62/361,628 2016-07-13
US15/644,908 US10872703B2 (en) 2016-07-13 2017-07-10 Moveable isolated rod couplings for use in a nuclear reactor control rod drive
US15/644,908 2017-07-10
CA3029845A CA3029845C (en) 2016-07-13 2017-07-13 Moveable isolated rod couplings for use in a nuclear reactor control rod drive

Related Parent Applications (1)

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CA3029845A Division CA3029845C (en) 2016-07-13 2017-07-13 Moveable isolated rod couplings for use in a nuclear reactor control rod drive

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CA3155316A1 CA3155316A1 (en) 2018-01-18
CA3155316C true CA3155316C (en) 2023-10-03

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CN112582086B (en) * 2020-12-11 2024-11-26 中广核研究院有限公司 Control rod drive mechanism with safety protection function

Family Cites Families (27)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3941653A (en) 1968-03-08 1976-03-02 Westinghouse Electric Corporation Control rod drive shaft latch
US3992255A (en) 1974-01-18 1976-11-16 Westinghouse Electric Corporation Control rod drive mechanism for a nuclear reactor
UST942002I4 (en) 1974-02-19 1976-01-06
US3933581A (en) 1974-06-04 1976-01-20 The United States Of America As Represented By The United States Energy Research And Development Administration Control rod drive for reactor shutdown
BE838037A (en) 1975-02-11 1976-05-14 PRESSURE TANK NUCLEAR REACTOR ADJUSTMENT BAR CONTROL
US4044622A (en) 1975-02-18 1977-08-30 Matthews John C Anti-ejection system for control rod drives
JPS51116393A (en) 1975-04-04 1976-10-13 Hitachi Ltd A control rod driving mechanism
FR2459535B1 (en) 1979-06-18 1986-08-08 Framatome Sa CYCLIC MOVEMENT FINGER MECHANISM FOR CONTROLLING A NUCLEAR REACTOR
FR2461334A1 (en) 1979-07-11 1981-01-30 Framatome Sa PINION AND RACK MECHANISM FOR DISPLACING A NEUTRON ABSORBING ASSEMBLY IN A NUCLEAR REACTOR
US4288898A (en) 1979-10-22 1981-09-15 The Babcock & Wilcox Company Control rod drive mechanism closure device
US4423002A (en) 1979-12-19 1983-12-27 Framatome Apparatus for controlling a nuclear reactor by vertical displacement of a unit absorbing neutrons
JPS57168192A (en) * 1981-04-09 1982-10-16 Nippon Kokan Kk Movable coil type control rod drive mechanism of reactor
US4518559A (en) 1982-07-08 1985-05-21 General Electric Company Control of nuclear reactors
US4484093A (en) 1982-12-08 1984-11-20 The United States Of America As Represented By The United States Department Of Energy Linear motion device and method for inserting and withdrawing control rods
JPS61215992A (en) * 1985-03-22 1986-09-25 日本鋼管株式会社 Method of controlling movable coil type control-rod drive
US5276719A (en) 1991-08-14 1994-01-04 Siemens Aktiengesellschaft Hydraulic control rod drive for a nuclear reactor
US5307384A (en) * 1992-12-16 1994-04-26 Westinghouse Electric Corp. Segmented coil assembly for control rod drive
US5428873A (en) 1993-04-29 1995-07-04 Bw/Ip International, Inc. Ball Latch mechanism
US5517536A (en) 1994-08-24 1996-05-14 General Electric Company Magnetic coupling device for control rod drive
US5778034A (en) 1995-12-26 1998-07-07 Kabushiki Kaisha Toshiba Control rod drive mechanism
US8757065B2 (en) 2006-03-30 2014-06-24 Raytheon Company Methods and apparatus for integrated locked thruster mechanism
US20080123795A1 (en) 2006-11-28 2008-05-29 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Controllable long term operation of a nuclear reactor
JP5171498B2 (en) 2008-09-12 2013-03-27 株式会社東芝 Control rod drive mechanism
US8811562B2 (en) 2010-03-12 2014-08-19 Babcock & Wilcox Nuclear Operations Group, Inc. Control rod drive mechanism for nuclear reactor
JP5537225B2 (en) 2010-03-31 2014-07-02 日立Geニュークリア・エナジー株式会社 Improved control rod drive mechanism handling device and method of handling the device
US9336910B2 (en) 2010-10-07 2016-05-10 Bwxt Nuclear Energy, Inc. Control rod/control rod drive mechanism couplings
JP6184346B2 (en) 2014-03-07 2017-08-23 日立Geニュークリア・エナジー株式会社 Control rod drive mechanism

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CA3029845A1 (en) 2018-01-18
WO2018013872A3 (en) 2018-02-22
GB2568611A (en) 2019-05-22
WO2018013872A2 (en) 2018-01-18
GB201900821D0 (en) 2019-03-13
JP2019534990A (en) 2019-12-05
GB2568611B (en) 2022-03-09
CA3029845C (en) 2022-08-09
CA3155316A1 (en) 2018-01-18
JP6895510B2 (en) 2021-06-30

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