GB1129565A - Device for inserting an emergency control rod into a nuclear reactor - Google Patents
Device for inserting an emergency control rod into a nuclear reactorInfo
- Publication number
- GB1129565A GB1129565A GB18602/66A GB1860266A GB1129565A GB 1129565 A GB1129565 A GB 1129565A GB 18602/66 A GB18602/66 A GB 18602/66A GB 1860266 A GB1860266 A GB 1860266A GB 1129565 A GB1129565 A GB 1129565A
- Authority
- GB
- United Kingdom
- Prior art keywords
- control rod
- support
- sleeves
- reactor
- inner sleeve
- 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
-
- 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
- G21C7/20—Disposition of shock-absorbing devices ; Braking arrangements
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Portable Nailing Machines And Staplers (AREA)
Abstract
1,129,565. Controlling reactors. SOCIETE D'ETUDE DE LA PROPULSION PAR REACTION, S.A. 28 April, 1966 [12 May, 1965], No. 18602/66. Heading G6C. A device for inserting an emergency control rod into a nuclear reactor comprises a telescopic assembly housing the control rod and being itself housed and guided within a cylindrical support fixed to the reactor superstructure in alignment with a duct provided in the interior of the reactor to receive the control rod, a chamber formed within the support and adapted to receive the combustion gases resulting from the explosion of an explosive cartridge within the device, the combustion gases causing the telescopic assembly to be extended and to propel the control rod towards the reactor interior, abutment means on the support and on the telescopic assembly for limiting movement of the latter within the support, and means for braking the control rod when it reaches its operative position in the duct. As shown in Figs. 1a, 1b, the telescopic assembly comprises outer and inner sleeves 9, 16, the former having its rear end enlarged to form a piston 10 which contacts the cylindrical support 1 and the latter having its rear end enlarged to form a piston 18 which contacts the outer sleeve 9. The inner sleeve 16 is fixed to a guide rod 7, on which a hollow control rod 6 is free to slide, and which extends into a duct 3 within the reactor core. A perforated guide member 8 is fixed to the front end of the guide rod 7. An explosive cartridge 24 is fixed to the rear end of the cylindrical support 1, a rear compartment of the inner sleeve 16 acting as an expansion chamber 25 for the combustion gases. End stops 13, 17 are provided on the front ends of the support 1 and outer sleeve 9 for the outer and inner sleeves, respectively. Resilient washers 15, 21 are provided on both sleeves for braking the sleeves and for forming a seal when movement has ceased. The annular space 19 between the two sleeves is connected by openings 20 near the front end of the outer sleeve with the annular space 12 between the outer sleeve and the cylindrical support which is, in turn, connected by openings 14 in the support with the atmosphere. The control rod 6 leaves the inner sleeve 16 directly this is stopped, sliding along the guide rod 7, a shoulder at the end of which enables the control rod to be decelerated at the end of its travel. The control rod is decelerated by means of brake discs or washers. In an alternative embodiment (not shown), the inner sleeve is fixed to but detachable from the front end of a propulsion device containing compressed CO 2 . The propulsion device is rigidly fixed to the cylindrical support and comprises a rear housing for an explosive cartridge and a chamber separated from the cartridge by a piston which fits closely and moves within this chamber. There is an annular V-groove where the propulsion device joins the inner sleeve. When the cartridge is fired, the piston compresses and heats the CO 2 until the inner sleeve separates from the gas bottle at the V-groove. The compressed CO 2 then drives both sleeves before it. The CO 2 is prevented by this means from liquefying as would occur in the course of a simple pressure-relief of CO 2 stored in the ambient conditions of the reactor.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR16738A FR1465388A (en) | 1965-05-12 | 1965-05-12 | Device for introducing a safety bar into a nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1129565A true GB1129565A (en) | 1968-10-09 |
Family
ID=8578562
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB18602/66A Expired GB1129565A (en) | 1965-05-12 | 1966-04-28 | Device for inserting an emergency control rod into a nuclear reactor |
Country Status (2)
Country | Link |
---|---|
FR (1) | FR1465388A (en) |
GB (1) | GB1129565A (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN112017799B (en) * | 2020-07-31 | 2022-03-11 | 清华大学 | Rod position measuring pressure bearing shell with adapter and control rod hydraulic drive system |
-
1965
- 1965-05-12 FR FR16738A patent/FR1465388A/en not_active Expired
-
1966
- 1966-04-28 GB GB18602/66A patent/GB1129565A/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
FR1465388A (en) | 1967-01-13 |
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