GB972474A - Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors - Google Patents

Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors

Info

Publication number
GB972474A
GB972474A GB8403/62A GB840362A GB972474A GB 972474 A GB972474 A GB 972474A GB 8403/62 A GB8403/62 A GB 8403/62A GB 840362 A GB840362 A GB 840362A GB 972474 A GB972474 A GB 972474A
Authority
GB
United Kingdom
Prior art keywords
gas
channel
ports
strips
valve
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
GB8403/62A
Inventor
Frank Hollins Buckley
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.)
WFEL Ltd
Original Assignee
Fairey Engineering 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 Fairey Engineering Ltd filed Critical Fairey Engineering Ltd
Priority to GB8403/62A priority Critical patent/GB972474A/en
Publication of GB972474A publication Critical patent/GB972474A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/02Details of handling arrangements
    • G21C19/04Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
    • 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)
  • Details Of Valves (AREA)

Abstract

972,474. Fuelling reactors. FAIREY ENGINEERING Ltd. June 5,1963 [March 5, 19621, No. 8403/62. Heading G6C. In order to prevent blow out of the fuel elements remaining in a reactor core channel after the majority of the elements in that charnel have been removed by a grab, the upward flow of coolant gas through the channel is automatically reduced by a valve responsive to the gas temperature. The valve is mounted at the lower end of a charge shoot adapted for connection to the channel and controls the flow from the channel into the space enclosed by the pressure vessel. At the normal working temperature of the gas in the channel corresponding to a fully loaded channel the valve is fully open but it closes progressively as the temperature drops as the fuel elements are removed. As shown, the lower end of a charge shoot 13 has a tubular extension 10 provided with ports 27 and surrounded by a fixed sleeve 15 having ports 25. Three annular members 20, 23, 24 are secured to the sleeve 15 and each annular member has four arcuate bimetallic strips 30 anchored thereto by rivets 32. The other ends of the strips 30 of each group are riveted at 33 to a ring 28 of L-section. At the normal working temperature of the gas the strips 30 are deflected so that the rings 28 are raised as seen in the right-hand half of Fig. 1 and the ports 25 are not obstructed. On cooling of the gas, however, the strips unflex so that the rings 28 drop and substantially close the ports 25 as shown in the left hand half of Fig. 1
GB8403/62A 1962-03-05 1962-03-05 Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors Expired GB972474A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB8403/62A GB972474A (en) 1962-03-05 1962-03-05 Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB8403/62A GB972474A (en) 1962-03-05 1962-03-05 Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors

Publications (1)

Publication Number Publication Date
GB972474A true GB972474A (en) 1964-10-14

Family

ID=9851880

Family Applications (1)

Application Number Title Priority Date Filing Date
GB8403/62A Expired GB972474A (en) 1962-03-05 1962-03-05 Improvements relating to automatic cooling gas control valves for gas-cooled nuclear reactors

Country Status (1)

Country Link
GB (1) GB972474A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4206658A1 (en) * 1992-03-03 1993-09-09 Siemens Ag SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK
DE4206660A1 (en) * 1992-03-03 1993-09-09 Siemens Ag SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4206658A1 (en) * 1992-03-03 1993-09-09 Siemens Ag SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK
DE4206660A1 (en) * 1992-03-03 1993-09-09 Siemens Ag SAFETY DEVICE AGAINST OVERPRESSURE FAILURE OF A CORE REACTOR PRESSURE TANK
US5517538A (en) * 1992-03-03 1996-05-14 Siemens Aktiengesellschaft Safety device protecting a nuclear reactor pressure vessel against overpressure failure
US5526385A (en) * 1992-03-03 1996-06-11 Siemens Aktiengesellschaft Safety device protecting against overpressure failure of a nuclear reactor pressure vessel

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