WO2018075107A2 - Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive - Google Patents
Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive Download PDFInfo
- Publication number
- WO2018075107A2 WO2018075107A2 PCT/US2017/041808 US2017041808W WO2018075107A2 WO 2018075107 A2 WO2018075107 A2 WO 2018075107A2 US 2017041808 W US2017041808 W US 2017041808W WO 2018075107 A2 WO2018075107 A2 WO 2018075107A2
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- drive
- control rod
- control element
- isolation barrier
- overtravel
- Prior art date
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Classifications
-
- 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
- G21C7/14—Mechanical drive arrangements
-
- 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
Definitions
- FIG. 1 is an illustration of a drive rod-control rod assembly (CRA) connection 10 useable with example embodiment control drives.
- 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 13, under force from the control rod drive mechanism.
- 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 as well as providing a vacuum environment for control rod drive elements outside the reactor.
- 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 selective coupling between the control element and a motor-driven linear drive. The selective coupling may use a latch with magnetic-selective coupling, such as magnetized plungers that hold the drive and control element together in a first position and release the two in a second position.
- the plungers may bias against and compress springs under magnetic force, and when the magnetic force, such as from external release coils or magnets, is released, the plungers may be driven back up by the springs and allow a releasing element, such as ball bearings or blocking elements, to slide back where the plunger diameter is now smaller and release the coupling. Otherwise, the plungers and blocking elements may maintain the joining configurations.
- 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 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.
- Example methods include applying a magnetic field to hold the latch in the joined configuration inside the isolation barrier.
- the latch and holding magnetic field on opposite sides of the isolation barrier may be moved by a common motor driving an interior and exterior rotor two which the two are respectively mounted.
- a linear screws may be independently driven by the rotors to move the latch and magnetic elements at a same vertical position.
- the latch When the magnetic element is de-energized or removed, the latch may release and 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.
- FIG. 1 is an illustration of a drive rod connection to a control rod assembly useable in example embodiments.
- FIG. 2 is a plan illustration of an example embodiment control rod drive mechanism using extended lift coils.
- FIG. 3 is a profile illustration of the example embodiment control rod drive mechanism using extended lift coils.
- FIG. 4 is another profile illustration of the example embodiment control rod drive mechanism using extended lift coils.
- 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
- example embodiment CRDM 200 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.
- Example embodiments described below uniquely enable solutions to these and other problems discovered by the Inventors.
- FIG. 2 is a plan view illustration of an example embodiment control rod drive mechanism (CRDM) 300.
- FIGS. 3 and 4 are profile views of the same example embodiment control rod drive mechanism 300 of FIG. 2, with FIG. 3 showing assembly 310 in a seated position and FIG. 4 showing assembly 310 in an overtravel position.
- Co-owned applications 15/640,428 filed June 30, 2017 to Morgan et al. for "STATIONARY ISOLATED ROD COUPLINGS FOR USE IN A NUCLEAR REACTOR CONTROL ROD DRIVE" and 15/644,908 filed July 10, 2017 to Morgan et al.
- a position of nut and ball latch 127 is established by zeroing position sensors 105 at a known position of lift rod 111 and latch 127 such as the overtravel position or the seated position at buffer assembly for scram force 101.
- nut and ball latch 127 will follow the scrammed lift rod 111 down to buffer assembly for scram force 101 (FIG. 3) and will drive itself down into the seated lift rod 111. This action resets CRDM 300 for further operation.
- Ball latch coils 128 may be re-energized before lift rod 111, drive rod 112, and CRA 310 are lifted out of buffer assembly for scram force 101.
- Lift rod 111 and drive rod 112 may be coupled to nut and ball latch 127 in CRDM 300 prior to coupling with CRA 310 as shown in FIG. 1.
- solenoid actuated release coil 102 fails to release drive rod 112 from CRA 310, an alternative mechanical actuation is available when shutdown.
- Motor 126, with associated brake and position sensors, and outer rotor 132 may be removed from above CRDM housing 106.
- the upper flange of CRDM housing 106 may be removed, and a tool may be run down through hollow inner rotor 133 and screw 131. The tool is threaded onto actuating rod 103, allowing it to be pulled while lift rod 111 and drive rod 112 position are held fast. This action compresses the spring(s) above the lower lock plug and frees the spud of CRA 310 from drive rod 112 for maintenance and repairs.
- CRA 310 is positioned by the motor-driven inner linear screw 131.
- Ball latch coils 128 mounted on outer linear screw 130 remain energized to keep the ball latch nut coupled to lift rod 111 within pressure boundary 150.
- CRDM motor 126 (FIG. 4) rotates inner rotor 133 (FIG. 4) and screw 131 within CRDM housing 106.
- the rotation of screw 131 causes vertical movement of ball latch 127 having a nut that is key ed to prevent rotation.
- Lift rod 111 travels with nut and ball latch 127 as long as balls 137 remain engaged.
- inner linear screw 131 when rotated by inner rotor 133 inside pressure boundary 150 moves and holds drive rod 112, lift rod 111, and CRA 310 therebelow by rotation and resultant linear movement of those features on threads inside pressure boundary 150.
- nut and ball latch 127 and outer energized ball latch coils 128 move vertically together on screw(s) 130 traversing the drive range or stroke distance.
- Feedback from position sensors of motor 126 and position indication probes 105 (FIG. 3) control rotation of motor 126 and move CRA 310 to its desired position for reactor control.
- Internal linear screw 131 and external linear screw 130 provide fine motion control of internal lift rod 111, drive rod 112, and CRA 310.
- Vacuum gap 121 (FIG. 2) between pressure boundary 150 and the ball latch coils 128 limits heat transfer between coils 128 and pressure boundary 150. This provides a more uniform temperature gradient on pressure boundary 150 that minimizes thermal cycling. Pressure boundary 150 wall thickness can be enhanced to minimize effects of corrosion, hydriding, and hydrogen deflagration problems.
- Reactor safety features requiring a scram provide inputs to the control system for the ball latch coils, normally energized to magnetically pair with magnetic elements. If reactor conditions warrant a scram, the control system de-energizes ball latch coils 128. This drops the ball latch magnetic field allowing spring-opposed plungers 141 to raise and retract the balls 137 supporting lift rod 111 shoulders. Gravitational force acts on lift rod 111, drive rod 112, and CRA 310, collapsing nut and ball latches 127 and dropping the unsupported components into a seated position on buffer assembly for scram force 101 (FIG. 3). Any failure causing a loss of current to ball latch coil 128 may also lead to a conservative control rod scram.
- Ball latch coils 128 may be continuously energized during operation and may be cooled by coolant inlet/outlet 107 through their travel range. Flexible lines of coolant inlet/outlet 107 may be oriented from the top of CRDM 300 and reach ball latch coils 128 through slotted openings of CRDM structural housing 106. These lines along with latch coil control circuits can have counter weights or spring reel feeds to keep them under slight tension during drive operation.
- drive rod 112 may be decoupled from CRA 310 as described above using solenoid actuated release coil 102 (FIG. 3).
- motor 126, linear screw(s) 131, and ball latch 127 are used to maneuver the coupled lift rod 111 and drive rod 112 to the overtravel position.
- two spring actuated overtravel latches 116 engage a shoulder or window in CRDM housing 106 to lock CRDM 300 at the overtravel height. Power and cooling can then be disconnected from or secured to motor 126 and ball latch coils 128 for a duration of the refueling process.
- the lower end of drive rod 112 may be carried to an elevation that is clear of the upper to lower vessel disassembly process.
- motor 126 and ball latch coils 128 may be energized to carry the weight of lift rod 111 and drive rod 112 in the overtravel position.
- Overtravel release coils 108 are then energized to compress spring actuated structural support 117 resting on pressure boundary 150 structural support as discussed above.
- CRDM Pressure Boundary 150 is supported vertically off of CRDM nozzle pressure boundary flange 120 in CRDM structural housing 106 of the RPV flange. Lateral support to upper portions of CRDM pressure boundar 150 may be provided by the close proximity of outer rotor 132 across vacuum gap 121. Inner rotor 133 (FIG. 4), inner linear screw 131, ball lath 127, and lift rod 111 may be laterally supported off walls of CRDM pressure boundary 150.
- CRDM structural housing 106 is also fixed to the 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 300.
- the internal bearings/bushings of outer linear screw(s) 130 (FIG. 3) are supported off 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 (FIG.
- Coolant inlet/outlet lines 107 are run to the fixed motor 126 which is located as remote as possible from the reactor's thermal and radiation output. Motor 126 is also isolated from CRDM pressure boundary- ISO by vacuum gap 121 to prevent conduction.
- 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 experimentation while still falling within the scope of the following claims.
- 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.
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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)
- Transmission Devices (AREA)
Abstract
Description
Claims
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CA3029827A CA3029827C (en) | 2016-07-13 | 2017-07-13 | Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive |
GB1900822.6A GB2570220B (en) | 2016-07-13 | 2017-07-13 | Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive |
JP2019501430A JP6773882B2 (en) | 2016-07-13 | 2017-07-13 | Magnetically actuated isolated rod coupling for use in reactor control rod drives |
Applications Claiming Priority (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US201662361604P | 2016-07-13 | 2016-07-13 | |
US62/361,604 | 2016-07-13 | ||
US15/646,117 | 2017-07-11 | ||
US15/646,117 US10770189B2 (en) | 2016-07-13 | 2017-07-11 | Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive |
Publications (2)
Publication Number | Publication Date |
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WO2018075107A2 true WO2018075107A2 (en) | 2018-04-26 |
WO2018075107A3 WO2018075107A3 (en) | 2018-07-26 |
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Application Number | Title | Priority Date | Filing Date |
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PCT/US2017/041808 WO2018075107A2 (en) | 2016-07-13 | 2017-07-13 | Magnetically-actuated isolated rod couplings for use in a nuclear reactor control rod drive |
Country Status (4)
Country | Link |
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JP (1) | JP6773882B2 (en) |
CA (1) | CA3029827C (en) |
GB (1) | GB2570220B (en) |
WO (1) | WO2018075107A2 (en) |
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KR101548060B1 (en) * | 2013-12-31 | 2015-08-27 | 한국원자력연구원 | Bottom mounted control rod drive device having permanent magnet inside electromagnet casing |
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2017
- 2017-07-13 JP JP2019501430A patent/JP6773882B2/en active Active
- 2017-07-13 GB GB1900822.6A patent/GB2570220B/en active Active
- 2017-07-13 WO PCT/US2017/041808 patent/WO2018075107A2/en active Application Filing
- 2017-07-13 CA CA3029827A patent/CA3029827C/en active Active
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Also Published As
Publication number | Publication date |
---|---|
CA3029827C (en) | 2021-03-23 |
WO2018075107A3 (en) | 2018-07-26 |
GB2570220A (en) | 2019-07-17 |
GB201900822D0 (en) | 2019-03-13 |
JP2019534988A (en) | 2019-12-05 |
GB2570220B (en) | 2022-01-05 |
CA3029827A1 (en) | 2018-04-26 |
JP6773882B2 (en) | 2020-10-21 |
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