GB1073557A - Improvements in and relating to the controlling systems for nuclear reactors - Google Patents
Improvements in and relating to the controlling systems for nuclear reactorsInfo
- 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
Links
Classifications
-
- 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
- G21C7/16—Hydraulic or pneumatic drive
-
- 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
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.
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)
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 |
-
1964
- 1964-08-19 LU LU46793D patent/LU46793A1/xx unknown
-
1965
- 1965-08-12 GB GB34515/65A patent/GB1073557A/en not_active Expired
- 1965-08-13 BE BE668276A patent/BE668276A/xx unknown
Cited By (5)
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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