GB1090632A - Nuclear reactor control mechanism - Google Patents

Nuclear reactor control mechanism

Info

Publication number
GB1090632A
GB1090632A GB32591/63A GB3259163A GB1090632A GB 1090632 A GB1090632 A GB 1090632A GB 32591/63 A GB32591/63 A GB 32591/63A GB 3259163 A GB3259163 A GB 3259163A GB 1090632 A GB1090632 A GB 1090632A
Authority
GB
United Kingdom
Prior art keywords
spring
rod
winch
pawls
control
Prior art date
Legal status (The legal status 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 status listed.)
Expired
Application number
GB32591/63A
Inventor
Herbert Chilvers Knights
Peter Highnam Crockett
William Joseph Sidebottom
Alan Richardson
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB32591/63A priority Critical patent/GB1090632A/en
Priority to BE651928D priority patent/BE651928A/xx
Publication of GB1090632A publication Critical patent/GB1090632A/en
Expired legal-status Critical Current

Links

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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • 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

Abstract

1,090,632. Reactor control rods. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. July 30, 1964 [Aug. 16, 1963 (2)], Nos. 32591/63 and 32592/63. Heading G6C. In a nuclear reactor control mechanism having a neutron absorbing body movable relative to the core by means of a flexible tie between it and the winch, the control rod is spring biased towards its active position, and withdrawn from this position, against the spring, by the winch and tie. The control unit is an integral structure housed in a casing 115 (Fig. 1), and retained in a standpipe 113 by balls 117. The unit contains a shield plug 120 penetrated by leads 119 for an electric motor 121, which drives a winch 122 to raise the safety rod 124 through chain or cable 127, against pressure from the spring 125. After initial insertion of the unit in the standpipe, the motor is energized to withdraw the safety rod 124 to its normal position within the casing 115. In an emergency, a clutch 123, between the winch and motor, is released, allowing the spring to force the safety rod into the core 111. Alternative drives.-In a first modification, the clutch and motor are replaced by two hydraulically actuated pawls which engage a ratchet wheel on the cable drum. One of the pawls allows winding-in rotation and prevents unwind of the drum. The other pawl is reciprocated, to wind the drum. For emergency shutdown, the first pawl is hydraulically withdrawn from the ratchet wheel, thus allowing the spring 125 to forcibly insert the safety rod. The second modification allows the associated rod to be used for normal reactivity control and for emergency shutdown. Wind-in is achieved as previously described, but a further hydraulic piston and cylinder unit actuates two pawls, each engaging a separate ratchet wheel, so as to allow tooth-by-tooth re-insertion of the control rod. A third hydraulic unit withdraws the pawls to enable the spring to rapidly insert the control rod.
GB32591/63A 1963-08-16 1963-08-16 Nuclear reactor control mechanism Expired GB1090632A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB32591/63A GB1090632A (en) 1963-08-16 1963-08-16 Nuclear reactor control mechanism
BE651928D BE651928A (en) 1963-08-16 1964-08-17

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB32591/63A GB1090632A (en) 1963-08-16 1963-08-16 Nuclear reactor control mechanism
GB3259263 1963-08-16

Publications (1)

Publication Number Publication Date
GB1090632A true GB1090632A (en) 1967-11-15

Family

ID=26261463

Family Applications (1)

Application Number Title Priority Date Filing Date
GB32591/63A Expired GB1090632A (en) 1963-08-16 1963-08-16 Nuclear reactor control mechanism

Country Status (2)

Country Link
BE (1) BE651928A (en)
GB (1) GB1090632A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4219384A (en) * 1976-11-06 1980-08-26 Hochtemperatur-Reaktorbau Gmbh Driving apparatus for an absorber rod
CN110718307A (en) * 2019-10-17 2020-01-21 中国科学院合肥物质科学研究院 Pre-stored energy reactivity control mechanism
CN111048220A (en) * 2019-12-31 2020-04-21 中国科学院合肥物质科学研究院 Disc type fast shutdown system
CN111081394A (en) * 2019-12-31 2020-04-28 中国核动力研究设计院 Reactivity control device for small nuclear reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4219384A (en) * 1976-11-06 1980-08-26 Hochtemperatur-Reaktorbau Gmbh Driving apparatus for an absorber rod
CN110718307A (en) * 2019-10-17 2020-01-21 中国科学院合肥物质科学研究院 Pre-stored energy reactivity control mechanism
CN111048220A (en) * 2019-12-31 2020-04-21 中国科学院合肥物质科学研究院 Disc type fast shutdown system
CN111081394A (en) * 2019-12-31 2020-04-28 中国核动力研究设计院 Reactivity control device for small nuclear reactor

Also Published As

Publication number Publication date
BE651928A (en) 1965-02-17

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