GB1073557A - Improvements in and relating to the controlling systems for nuclear reactors - Google Patents

Improvements in and relating to the controlling systems for nuclear reactors

Info

Publication number
GB1073557A
GB1073557A GB34515/65A GB3451565A GB1073557A GB 1073557 A GB1073557 A GB 1073557A GB 34515/65 A GB34515/65 A GB 34515/65A GB 3451565 A GB3451565 A GB 3451565A GB 1073557 A GB1073557 A GB 1073557A
Authority
GB
United Kingdom
Prior art keywords
tube
rod
tubing
primary
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
GB34515/65A
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.)
ANGLO BELGE VULCAIN SOC
Original Assignee
ANGLO BELGE VULCAIN SOC
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 ANGLO BELGE VULCAIN SOC filed Critical ANGLO BELGE VULCAIN SOC
Publication of GB1073557A publication Critical patent/GB1073557A/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
    • G21C7/16Hydraulic or pneumatic drive
    • 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

1,073,557. Controlling reactwrs. SOC. ANGLO-BELGE VULCAIN, SOC. ANON. Aug. 12, 1965 [Aug. 19, 1964], No. 34515/65. Heading G6C. [Also in Division F2] A neutron-absorbing rod 1 is hydraulically actuated in a nuclear reactor by a system in which differential pressures in the primary fluid circuit of the reactor displace the rod in a guide tube 2 through which the primary fluid flows, this flow being controlled by a master valve 3 connecting one end of the guide tube 2 by means of tubes 4, 5 to one of two regions of the primary circuits in which prevail respectively a pressure lower than and a pressure higher than that prevailing at the other end of the tube. The primary fluid is a fluid effecting removal of heat from the core and/or its moderation and/or its temperature regulation. The master valve 3 is connected with a pilot valve 9 which controls the position of the slide of the master valve 3 in such a manner as to establish a variable orifice between the top of the tube 2 and either the tubing 4 or the tubing 5. The pilot valve 9 is itself connected with the primary circuit respectively upstream and downstream of the primary fluid circulating pump 12. The feeding of the pilot valve 9 is effected automatically or by hand by means of valves 13, 14. When it is desired to raise the rod 1 or to maintain it in a predetermined position in the tube 2, the pilot valve 9 is operated such that the slide of the master valve 3 is placed in a position for which an opening of predetermined size established communication between the top of the tube 2 and the tubing 4 connected to the lowpressure region of the primary circuit. When it is desired to introduce the rod into the core, the pilot valve 9 is operated such that the slide of the master valve 3 is placed in a position for which communication is established between the top of the tube 2 and the tubing 5 connected to the high pressure region of the primary circuit. The system is fail-safe because any absence of pressure for actuating the slide of the master valve (e.g. rupture of a conduit) involves its displacement to a position connecting the top of the tube 2 with the tubing 5 resulting in the rod being inserted into the core, and any absence of pressure of the primary fluid results in automatic introduction of the rod into the core under the action of gravity.
GB34515/65A 1964-08-19 1965-08-12 Improvements in and relating to the controlling systems for nuclear reactors Expired GB1073557A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
LU46793 1964-08-19

Publications (1)

Publication Number Publication Date
GB1073557A true GB1073557A (en) 1967-06-28

Family

ID=19723933

Family Applications (1)

Application Number Title Priority Date Filing Date
GB34515/65A Expired GB1073557A (en) 1964-08-19 1965-08-12 Improvements in and relating to the controlling systems for nuclear reactors

Country Status (3)

Country Link
BE (1) BE668276A (en)
GB (1) GB1073557A (en)
LU (1) LU46793A1 (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3793141A (en) * 1972-09-29 1974-02-19 Babcock & Wilcox Co Nuclear reactor control system
US4439054A (en) * 1980-12-16 1984-03-27 Westinghouse Electric Corp. Latching mechanism
US4550941A (en) * 1980-12-16 1985-11-05 Westinghouse Electric Corp. Hydraulic drive mechanism
CN105551553A (en) * 2015-12-15 2016-05-04 中广核工程有限公司 Pilot type safety valve jumping monitoring device and method of PWR (Pressured Water Reactor) nuclear power station

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3793141A (en) * 1972-09-29 1974-02-19 Babcock & Wilcox Co Nuclear reactor control system
US4439054A (en) * 1980-12-16 1984-03-27 Westinghouse Electric Corp. Latching mechanism
US4550941A (en) * 1980-12-16 1985-11-05 Westinghouse Electric Corp. Hydraulic drive mechanism
CN105551553A (en) * 2015-12-15 2016-05-04 中广核工程有限公司 Pilot type safety valve jumping monitoring device and method of PWR (Pressured Water Reactor) nuclear power station
CN105551553B (en) * 2015-12-15 2018-06-29 中广核工程有限公司 Pressurized-water reactor nuclear power plant pilot operated safety valve take-off monitoring device and method

Also Published As

Publication number Publication date
LU46793A1 (en) 1966-02-19
BE668276A (en) 1966-02-14

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