GB872092A - Improvements in and relating to safety release mechanisms - Google Patents

Improvements in and relating to safety release mechanisms

Info

Publication number
GB872092A
GB872092A GB28768/58A GB2876858A GB872092A GB 872092 A GB872092 A GB 872092A GB 28768/58 A GB28768/58 A GB 28768/58A GB 2876858 A GB2876858 A GB 2876858A GB 872092 A GB872092 A GB 872092A
Authority
GB
United Kingdom
Prior art keywords
rod
control rod
tube
push
pressure
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
GB28768/58A
Inventor
Stephen Baldwin Dunwi Fletcher
Deric Birkenshaw
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.)
Nuclear Power Plant Co Ltd
Original Assignee
Nuclear Power Plant Co Ltd
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 Nuclear Power Plant Co Ltd filed Critical Nuclear Power Plant Co Ltd
Priority to GB28768/58A priority Critical patent/GB872092A/en
Priority to ES0251757A priority patent/ES251757A1/en
Priority to FR804228A priority patent/FR1234552A/en
Priority to DEN17192A priority patent/DE1142423B/en
Priority to BE582423A priority patent/BE582423A/en
Publication of GB872092A publication Critical patent/GB872092A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • G21C19/105—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements with grasping or spreading coupling elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
    • 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

Abstract

872,092. Controlling reactors. NUCLEAR POWER PLANT CO. Ltd. Aug. 14, 1959 [Sept. 8, 1958], No. 28768/58. Class 39(4). A safety release mechanism for releasing a member from a parent member in response to changes in pressure in a fluid in which the releasable member is immersed comprises a push rod attached to the releasable member and operable to trip a latch mechanism joining the releasable member to the parent member and a pressure sensitive device located in the releasable member and forming an enclosed space therein; the pressure sensitive device being responsive to pressure changes between the enclosed space and fluid surrounding the releasable member and exerting a force on the push rod sufficient to trip the latch mechanism when a predetermined pressure change occurs. Fig. 1 shows an arrangement for releasing a control or safety rod in a gascooled nuclear reactor. The control rod comprises a tube 2 containing boron and arranged between inner and outer stainless steel tubes 1, 3. The outer tube 1 is welded to a tube 21 attached to a lifting head 13. A bellows 6 provided with an orifice 9 forms an enclosed chamber within the control rod so that if the gas pressure outside the rod falls, the bellows expand pushing up push rods 10 which act on a plate 15 and a further push rod 14 to actuate a latch mechanism and release the control rod. If the temperature of the gas around the control rod rises excessively tube 21 expands thus causing an end cap 11 to press down on the ends of levers 26 which push up the rods 10 and release the control rod. To retrieve the rod from the reactor the member 20 is lowered by a rope or chain until it contacts the top of the rod where, due to the geometry of the system, the pawls 24 under the weight of member 20 are rotated into the locking position by cam action of the pawls 24 on the inclined faces of lifting head 13.
GB28768/58A 1958-09-08 1958-09-08 Improvements in and relating to safety release mechanisms Expired GB872092A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
GB28768/58A GB872092A (en) 1958-09-08 1958-09-08 Improvements in and relating to safety release mechanisms
ES0251757A ES251757A1 (en) 1958-09-08 1959-08-29 Improvements in and relating to safety release mechanisms
FR804228A FR1234552A (en) 1958-09-08 1959-09-03 Safety release mechanism
DEN17192A DE1142423B (en) 1958-09-08 1959-09-05 Safety device in nuclear reactors
BE582423A BE582423A (en) 1958-09-08 1959-09-07 Improvements relating to mechanical safety release devices.

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB28768/58A GB872092A (en) 1958-09-08 1958-09-08 Improvements in and relating to safety release mechanisms

Publications (1)

Publication Number Publication Date
GB872092A true GB872092A (en) 1961-07-05

Family

ID=10280839

Family Applications (1)

Application Number Title Priority Date Filing Date
GB28768/58A Expired GB872092A (en) 1958-09-08 1958-09-08 Improvements in and relating to safety release mechanisms

Country Status (4)

Country Link
DE (1) DE1142423B (en)
ES (1) ES251757A1 (en)
FR (1) FR1234552A (en)
GB (1) GB872092A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1207026B (en) * 1961-11-16 1965-12-16 Westinghouse Electric Corp Ratchet coupling for connecting a control rod for nuclear reactors moving in a guide tube with a hollow drive shaft
US4167443A (en) * 1977-08-30 1979-09-11 Combustion Engineering, Inc. Self-actuated rate of change of pressure scram device for nuclear reactors
US4476088A (en) * 1979-10-30 1984-10-09 Nuclear Power Company Limited Latching devices and nuclear reactors incorporating such latching devices
US7891607B2 (en) 2006-10-18 2011-02-22 The Boeing Company Pressure sensor device
GB2508815A (en) * 2012-12-11 2014-06-18 Rolls Royce Plc A pressure sensitive actuator for use in nuclear reactor systems

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2590715B1 (en) * 1985-11-28 1988-01-15 Commissariat Energie Atomique DEVICE FOR AUTOMATICALLY TRIGGERING THE FALL OF AN ABSORBENT ELEMENT IN THE HEART OF A NUCLEAR REACTOR
IT1231553B (en) * 1989-04-13 1991-12-17 Enea AUTOMATIC RELEASE MECHANISM FOR CONTROL BARS IN A NUCLEAR REACTOR

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE855785C (en) * 1950-06-17 1952-11-17 Herbert Schoen Electromechanical screw jack
GB786486A (en) * 1954-05-11 1957-11-20 Atomic Energy Authority Uk Improvements in or relating to nut and screw mechanisms
US2794670A (en) * 1954-06-30 1957-06-04 Robert L Menegus Releasable holder for rod
GB795565A (en) * 1956-02-02 1958-05-28 Atomic Energy Authority Uk Improvements in or relating to control mechanisms for nuclear reactors

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1207026B (en) * 1961-11-16 1965-12-16 Westinghouse Electric Corp Ratchet coupling for connecting a control rod for nuclear reactors moving in a guide tube with a hollow drive shaft
US4167443A (en) * 1977-08-30 1979-09-11 Combustion Engineering, Inc. Self-actuated rate of change of pressure scram device for nuclear reactors
US4476088A (en) * 1979-10-30 1984-10-09 Nuclear Power Company Limited Latching devices and nuclear reactors incorporating such latching devices
US7891607B2 (en) 2006-10-18 2011-02-22 The Boeing Company Pressure sensor device
GB2508815A (en) * 2012-12-11 2014-06-18 Rolls Royce Plc A pressure sensitive actuator for use in nuclear reactor systems

Also Published As

Publication number Publication date
DE1142423B (en) 1963-01-17
ES251757A1 (en) 1960-01-01
FR1234552A (en) 1960-10-18

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