[go: up one dir, main page]

GB1327196A - Safety devices for nuclear reactors - Google Patents

Safety devices for nuclear reactors

Info

Publication number
GB1327196A
GB1327196A GB5046369A GB1327196DA GB1327196A GB 1327196 A GB1327196 A GB 1327196A GB 5046369 A GB5046369 A GB 5046369A GB 1327196D A GB1327196D A GB 1327196DA GB 1327196 A GB1327196 A GB 1327196A
Authority
GB
United Kingdom
Prior art keywords
rod
strut
reactor
support tube
pressure vessel
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
GB5046369A
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.)
Reyrolle Parsons Ltd
Original Assignee
Reyrolle Parsons 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 Reyrolle Parsons Ltd filed Critical Reyrolle Parsons Ltd
Publication of GB1327196A publication Critical patent/GB1327196A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C9/04Means for suppressing fires ; Earthquake protection
    • 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
    • G21C9/027Means 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
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1327196 Controlling reactors REYROLLE PARSONS Ltd 6 Jan 1971 [14 Oct 1969] 50463/69 Heading G6C A reactor safety device operates automatically in response to a relative displacement between the reactor pressure vessel and the superstructure above it from which the control rods are suspended, for releasing the control rods to allow them to fall under gravity into the reactor core in response to the occurrence of a relative displacement in excess of a predetermined amount. In the embodiment shown, a control rod 10 is releasably latched within the lower end of a support tube 11 by means of three latch members 13 whose heads are held against a chamfered abutment 14 inside the support tube 11 by means of a conical end 15 on a plunger rod 16. The latch members 13 have cross-bars 13A at thier lower end which are engaged in an annular recess 10A beneath abutment surfaces in the head of the control rod 10. The rod 16 is biased upwardly by means of a spring 21 which bears against an abutment portion 22 of the rod 16 and a ring 23 biased within the support tube 11. The upper end of the rod 16 is tapered at 16A and has a flat end face 24 on which the conical end 25A of a detent strut 25 abuts. The upper end of the strut 25 is attached by a chain (not shown) to a motor-driven winch on a concrete superstructure above the pressure vessel. The strut 25 has a part-spherical intermediate portion 26 which bears against an inwardly tapering end cap 27 screwed to the top of support tube 11 and thus forms a fulcrum about which the strut 25 may move. Upon the occurrence of a displacement of the superstructure relative to the pressure vessel, caused for example by an earthquake, an explosion in the vicinity of the reactor or a structural fault in some part of the reactor, a tilting of the strut 25 will occur about the fulcrum 26 causing its conical end 25A to move across the face 24 of the plunger rod 16. Should the tilting exceed a predetermined amount, e.g. 2 degrees, the end 25A will move beyond the edge of the face 24 and the rod 16 will be driven upwards by the spring 21 thus releasing the latch members 13 and allowing the control rod 10 to fall into the reactor core.
GB5046369A 1969-10-14 1969-10-14 Safety devices for nuclear reactors Expired GB1327196A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB5046369 1969-10-14

Publications (1)

Publication Number Publication Date
GB1327196A true GB1327196A (en) 1973-08-15

Family

ID=10455984

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5046369A Expired GB1327196A (en) 1969-10-14 1969-10-14 Safety devices for nuclear reactors

Country Status (1)

Country Link
GB (1) GB1327196A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4019954A (en) * 1974-11-07 1977-04-26 Commissariat A L'energie Atomique Safety device for a nuclear reactor and especially a fast reactor
CN108922638A (en) * 2018-07-25 2018-11-30 中广核研究院有限公司 A kind of control rod drive mechanism with auxiliary scram device
CN111916228A (en) * 2020-07-31 2020-11-10 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) Drive rod group on control rod drive mechanism and offshore reactor

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4019954A (en) * 1974-11-07 1977-04-26 Commissariat A L'energie Atomique Safety device for a nuclear reactor and especially a fast reactor
CN108922638A (en) * 2018-07-25 2018-11-30 中广核研究院有限公司 A kind of control rod drive mechanism with auxiliary scram device
CN108922638B (en) * 2018-07-25 2024-05-17 中广核研究院有限公司 Control rod driving mechanism with auxiliary rod falling device
CN111916228A (en) * 2020-07-31 2020-11-10 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) Drive rod group on control rod drive mechanism and offshore reactor
CN111916228B (en) * 2020-07-31 2023-06-06 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) Driving rod group on control rod driving mechanism and offshore reactor

Similar Documents

Publication Publication Date Title
US3607639A (en) Fuel assembly for nuclear reactors
GB1115492A (en) Nuclear reactor core clamping system
GB1327196A (en) Safety devices for nuclear reactors
GB1170879A (en) Improvements in or relating to nuclear reactors.
US4659538A (en) Apparatus for limiting the effect of axial hydraulic flow force exerted on fuel assemblies of water-cooled nuclear reactors
GB1264455A (en)
US4019954A (en) Safety device for a nuclear reactor and especially a fast reactor
CH513493A (en) Device for monitoring the operation of a drive device of a control rod arranged in a gas-cooled nuclear reactor and serving as a regulating and emergency shutdown rod
GB1039904A (en) Improvements in or relating to load-engaging devices for remote engagement of loads,more particularly radioactive loads, such as radioactive waste or the like
GB975648A (en) Neutron absorbing rod for nuclear reactors
GB978443A (en) Braking device for falling objects
US3096268A (en) Arresting devices for falling bodies
US4834934A (en) Thimble grip fuel assembly handling tool
JPH07209462A (en) Fuel assembly for pressurized water reactor
ES8702064A1 (en) Refueling of nuclear reactors.
GB965344A (en) Improvements in or relating to coupling mechanisms
Wilcox Improvements relating to safety devices for nuclear reactors
GB872092A (en) Improvements in and relating to safety release mechanisms
GB889702A (en) A control and shut-down device for a nuclear reactor
GB1462710A (en) Safety device for a nuclear reactor
GB860691A (en) Improvements relating to shock absorbing devices
GB915362A (en) Improvements in or relating to safety devices for nuclear reactors
GB1513971A (en) Assemblies for use in nuclear reactors
GB913897A (en) Improvements in or relating to gas-cooled nuclear reactors
GB1583306A (en) Safety apparatus for a nuclear reactor

Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PLNP Patent lapsed through nonpayment of renewal fees