WO2018013872A2 - 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 PDFInfo
- Publication number
- WO2018013872A2 WO2018013872A2 PCT/US2017/042023 US2017042023W WO2018013872A2 WO 2018013872 A2 WO2018013872 A2 WO 2018013872A2 US 2017042023 W US2017042023 W US 2017042023W WO 2018013872 A2 WO2018013872 A2 WO 2018013872A2
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- control rod
- isolation barrier
- overtravel
- induction coil
- control element
- 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.
- 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.
- 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.
- the induction coil 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.
- the control element 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.
- 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 environment for the mechanical drives that typically must operate to move control rods over a period of several months or years without maintenance.
- reactor temperatures, leaked coolant, and noncondensible gasses found inside 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.
- the Inventors have newly recognized a need for a control rod drive that has less engagement with example embodiment CRDM 200 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.
- 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.
- Co-owned application 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” is incorporated herein by reference in its entirety. Descriptions of actuating rod 103, position indication magnet 115, lift rod actuating magnet 104, key features 118, are given in the incorporated '428 application
- CRA 210 is positioned by outer linear screw 123 and scram lift coils 113.
- 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 CRDM 200 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 111, drive rod 112, and CRA 210 follow the magnetic field.
- Feedback from position sensors and position indication probes 105 control outer linear screw 123 rotation and move CRA 210 in CRDM 200 to its desired position for reactor control.
- Outer linear screw 123 provides fine motion control of internal lift rod 111, drive rod 112 and CRA 210.
- Vacuum 121 may provide a more uniform temperature gradient on example embodiment CRDM 200 pressure boundary 150 that minimizes thermal cycling.
- 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.
- 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 111, drive rod 112, 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.
- 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.
- Drive rod 111 may be decoupled from CRA 210 as described in the incorporated '428 application. 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 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 112 is carried to an elevation that is clear of the upper to lower vessel disassembly process.
- 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 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.
- 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.
- 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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- 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
Description
Claims
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2019501722A JP6895510B2 (en) | 2016-07-13 | 2017-07-13 | Movable isolated rod coupling for use in reactor control rod drives |
CA3029845A CA3029845C (en) | 2016-07-13 | 2017-07-13 | Moveable isolated rod couplings for use in a nuclear reactor control rod drive |
GB1900821.8A GB2568611B (en) | 2016-07-13 | 2017-07-13 | Moveable isolated rod couplings for use in a nuclear reactor control rod drive |
Applications Claiming Priority (4)
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 |
Publications (2)
Publication Number | Publication Date |
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WO2018013872A2 true WO2018013872A2 (en) | 2018-01-18 |
WO2018013872A3 WO2018013872A3 (en) | 2018-02-22 |
Family
ID=60953377
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/US2017/042023 WO2018013872A2 (en) | 2016-07-13 | 2017-07-13 | Moveable isolated rod couplings for use in a nuclear reactor control rod drive |
Country Status (4)
Country | Link |
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JP (1) | JP6895510B2 (en) |
CA (2) | CA3155316C (en) |
GB (1) | GB2568611B (en) |
WO (1) | WO2018013872A2 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2022122015A1 (en) * | 2020-12-11 | 2022-06-16 | 中广核研究院有限公司 | Control rod driving mechanism with safety protection function |
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- 2017-07-13 CA CA3155316A patent/CA3155316C/en active Active
- 2017-07-13 WO PCT/US2017/042023 patent/WO2018013872A2/en active Application Filing
- 2017-07-13 CA CA3029845A patent/CA3029845C/en active Active
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2022122015A1 (en) * | 2020-12-11 | 2022-06-16 | 中广核研究院有限公司 | Control rod driving mechanism with safety protection function |
Also Published As
Publication number | Publication date |
---|---|
CA3155316C (en) | 2023-10-03 |
CA3029845C (en) | 2022-08-09 |
GB201900821D0 (en) | 2019-03-13 |
JP6895510B2 (en) | 2021-06-30 |
GB2568611A (en) | 2019-05-22 |
CA3029845A1 (en) | 2018-01-18 |
JP2019534990A (en) | 2019-12-05 |
WO2018013872A3 (en) | 2018-02-22 |
GB2568611B (en) | 2022-03-09 |
CA3155316A1 (en) | 2018-01-18 |
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