GB821655A - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- GB821655A GB821655A GB30853/56A GB3085356A GB821655A GB 821655 A GB821655 A GB 821655A GB 30853/56 A GB30853/56 A GB 30853/56A GB 3085356 A GB3085356 A GB 3085356A GB 821655 A GB821655 A GB 821655A
- Authority
- GB
- United Kingdom
- Prior art keywords
- plug
- control rod
- shield plug
- shield
- hoist
- 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
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16H—GEARING
- F16H25/00—Gearings comprising primarily only cams, cam-followers and screw-and-nut mechanisms
- F16H25/18—Gearings comprising primarily only cams, cam-followers and screw-and-nut mechanisms for conveying or interconverting oscillating or reciprocating motions
- F16H25/20—Screw mechanisms
- F16H25/22—Screw mechanisms with balls, rollers, or similar members between the co-operating parts; Elements essential to the use of such members
- F16H25/2204—Screw mechanisms with balls, rollers, or similar members between the co-operating parts; Elements essential to the use of such members with balls
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16H—GEARING
- F16H25/00—Gearings comprising primarily only cams, cam-followers and screw-and-nut mechanisms
- F16H25/18—Gearings comprising primarily only cams, cam-followers and screw-and-nut mechanisms for conveying or interconverting oscillating or reciprocating motions
- F16H25/20—Screw mechanisms
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements 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
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/22—Arrangements for obtaining access to the interior of a pressure vessel whilst the reactor is operating
-
- 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
-
- 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
- G21C7/14—Mechanical drive 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
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Mechanical Engineering (AREA)
- Load-Engaging Elements For Cranes (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Transmission Devices (AREA)
Abstract
821,655. Nuclear reactors. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. Oct. 18, 1957 [Oct. 10, 1956], No. 30853/56. Class 39(4). [Also in Group XXV] A shield plug for a nuclear reactor comprises means for raising a control rod and holding it at the lower end of the plug. The plug consists of an upper section 6 containing radiationabsorbent material, a centre section 7 containing further absorbent material and a lower section 8 containing means for holding a raised control rod in place. Preparatory to re-fuelling a channel of the reactor it is necessary to remove the control rod and its shield plug and for this purpose an auxiliary transfer hoist shown in Fig. 6 is placed over the shield plug. A cable 5 attached to the top of the control rod is secured to the drum 135 of this hoist by a pin 142. By means of an operating cable 137 the control rod is then raised until it can be held on a support 3. A hook (see Group XXV) is then lowered through an aperture 153 in the casing of the hoist and coupled to a bar 81 in the top of the shield plug. The plug can then be removed from the reactor so that re-fuelling can take place. During and after removal the shield plug is held in a gland tube the access hole of which is subsequently closed. The control rod support 3 forms a flap, which is raised or lowered by a rod 2, the upper end of which is associated with a quadrant 71 forming an interlock to prevent incorrect operation of the flap. Heat baffle plates 41 are located between the lowest and middle sections of the plug and an idler pulley 19 between the top and middle sections.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB13669/54A GB786486A (en) | 1954-05-11 | 1954-05-11 | Improvements in or relating to nut and screw mechanisms |
Publications (1)
Publication Number | Publication Date |
---|---|
GB821655A true GB821655A (en) | 1959-10-14 |
Family
ID=10027257
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB13669/54A Expired GB786486A (en) | 1954-05-11 | 1954-05-11 | Improvements in or relating to nut and screw mechanisms |
GB30853/56A Expired GB821655A (en) | 1954-05-11 | 1956-10-10 | Improvements in or relating to nuclear reactors |
Family Applications Before (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB13669/54A Expired GB786486A (en) | 1954-05-11 | 1954-05-11 | Improvements in or relating to nut and screw mechanisms |
Country Status (4)
Country | Link |
---|---|
BE (1) | BE551683A (en) |
FR (1) | FR1161179A (en) |
GB (2) | GB786486A (en) |
NL (1) | NL99908C (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3243353A (en) * | 1961-04-10 | 1966-03-29 | Costes Didier | Fluid-tight access means for a nuclear reactor |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB872092A (en) * | 1958-09-08 | 1961-07-05 | Nuclear Power Plant Co Ltd | Improvements in and relating to safety release mechanisms |
GB915808A (en) * | 1959-07-09 | 1963-01-16 | Havilland Engine Co Ltd | Control in nuclear reactors |
US3053104A (en) * | 1959-08-06 | 1962-09-11 | Creusot Forges Ateliers | Device for producing regulated rectilinear movements |
FR1241783A (en) * | 1959-08-06 | 1960-09-23 | Creusot Forges Ateliers | Device for performing controlled rectilinear movements |
NL200864A (en) * | 1960-02-05 | |||
CN102117668B (en) * | 2009-12-31 | 2014-08-27 | 中国核动力研究设计院 | Reactor core unloading tool |
-
1954
- 1954-05-11 GB GB13669/54A patent/GB786486A/en not_active Expired
-
1956
- 1956-10-08 FR FR1161179D patent/FR1161179A/en not_active Expired
- 1956-10-10 GB GB30853/56A patent/GB821655A/en not_active Expired
- 1956-10-10 BE BE551683A patent/BE551683A/xx unknown
- 1956-10-10 NL NL211299A patent/NL99908C/xx active
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3243353A (en) * | 1961-04-10 | 1966-03-29 | Costes Didier | Fluid-tight access means for a nuclear reactor |
Also Published As
Publication number | Publication date |
---|---|
NL211299A (en) | 1961-07-17 |
FR1161179A (en) | 1958-08-22 |
BE551683A (en) | 1956-10-31 |
GB786486A (en) | 1957-11-20 |
NL99908C (en) | 1961-12-15 |
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