GB1205731A - Nuclear reactor control device - Google Patents
Nuclear reactor control deviceInfo
- Publication number
- GB1205731A GB1205731A GB469/69A GB46969A GB1205731A GB 1205731 A GB1205731 A GB 1205731A GB 469/69 A GB469/69 A GB 469/69A GB 46969 A GB46969 A GB 46969A GB 1205731 A GB1205731 A GB 1205731A
- Authority
- GB
- United Kingdom
- Prior art keywords
- rods
- trim
- pistons
- electromagnets
- core position
- 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
- 230000007246 mechanism Effects 0.000 abstract 5
- 230000000712 assembly Effects 0.000 abstract 4
- 238000000429 assembly Methods 0.000 abstract 4
- 230000004907 flux Effects 0.000 abstract 4
- 239000000446 fuel Substances 0.000 abstract 4
- 239000006096 absorbing agent Substances 0.000 abstract 1
- 230000009471 action Effects 0.000 abstract 1
- 230000005484 gravity Effects 0.000 abstract 1
- 239000000696 magnetic material Substances 0.000 abstract 1
- 230000004048 modification Effects 0.000 abstract 1
- 238000012986 modification Methods 0.000 abstract 1
- 230000035515 penetration Effects 0.000 abstract 1
- 229910001220 stainless steel Inorganic materials 0.000 abstract 1
- 239000010935 stainless steel Substances 0.000 abstract 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F15—FLUID-PRESSURE ACTUATORS; HYDRAULICS OR PNEUMATICS IN GENERAL
- F15B—SYSTEMS ACTING BY MEANS OF FLUIDS IN GENERAL; FLUID-PRESSURE ACTUATORS, e.g. SERVOMOTORS; DETAILS OF FLUID-PRESSURE SYSTEMS, NOT OTHERWISE PROVIDED FOR
- F15B21/00—Common features of fluid actuator systems; Fluid-pressure actuator systems or details thereof, not covered by any other group of this subclass
- F15B21/08—Servomotor systems incorporating electrically operated control means
-
- 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
-
- 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
-
- 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
- G21C7/10—Construction of control elements
- G21C7/117—Clusters of control rods; Spider construction
-
- 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
-
- 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)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Analytical Chemistry (AREA)
- Fluid Mechanics (AREA)
- Mechanical Engineering (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Magnetically Actuated Valves (AREA)
Abstract
1,205,731. Controlling reactors. WESTING- HOUSE ELECTRIC CORP. 3 Jan., 1969 [24 Jan., 1968 (2)], No. 469/69. Heading G6C. A nuclear reactor has disposed within a vessel a reactor core including a plurality of fuel assemblies each having a number of separately movable control rods, at least one drive mechanism for moving the control rods and means for holding selected control rods in predetermined positions, the or each drive mechanism having a drive train extending into the reactor vessel and adapted to engage at least some of the separately movable control rods in at least one of the fuel assemblies for movement of the control rods engaged by the drive train, but not held by the holding means. In one embodiment, the fuel assemblies each include a plurality of guide tubes which house either rod cluster control units for primary and shutdown control or fine flux trim rods. The guide tubes housing fine flux trim rods from a number of fuel assemblies are connected by curved guide channels with the upper guideway extensions 92 of a drive mechanism 64 (Fig. 5) mounted on a head penetration adaptor of the reactor vessel. Pistons 74 are attached at their lower ends to ball cables 78 which are in turn attached at their lower ends to the fine flux trim rods (not shown). The trim rods in their in-core position hang on the ball cables 78 attached to pistons 74, which are supported on a ledge, and are moved to their out-of-core position (r.h.s. in Fig. 5) through the extensions 92. The force required to lift the pistons 74 is obtained by connecting an upper cavity 94 with a low pressure water retention tank 96. Energizing the coil 98 of an electromagnetic valve 100 lifts a tapered valve tip 102 from its associated seat 104. Connection is then made through channels 106, 107 between the cavity 94 and the tank 96. The trim rods are selectively returned to their in-core position under the action of gravity when the coil 98 is de-energized. A plurality of electromagnets 114 is arranged symmetrically about the mechanism head, one electromagnet being positioned adjacent the top position of each piston 74. When the coils 118 of the electromagnets 114 are energized, the corresponding pistons 74 are pulled towards the polepieces 116. A tapered portion 120 of the piston 74 abuts a ledge 122 which aids in holding the piston in its top position. If one or more trim rods must be withdrawn from the in-core position, it is first necessary in this embodiment to withdraw all the rods by opening the valve 100 and then to selectively energize the magnetic coils 118 to hold in the out-of-core position those rods which are to remain withdrawn. An A.C. signal may be superimposed on the D.C. current of the electromagnets 114 to ascertain which pistons 74 are in their uppermost position, the coil impedance being higher in the latter case than when a piston has been accidentally dropped or has been unable to complete its upward movement due to some mechanical misalignment. In a modification, the necessity of lifting all the trim rods when withdrawal of less than all is desired is eliminated by providing electromagnets at the location of the pistons when the rods are in their in-core position. It is then only necessary to energize selectively those electromagnets associated with the trim rods which are to remain in the core, before opening the valve 100. In an alternative embodiment, the trim rods are suspended from a movable block of magnetic material disposed in a housing and a magnetic structure comprising at least one electromagnet is located exteriorly of and movable along the housing. This mechanism accomplishes the same functions as its hydraulic counterpart in the first embodiment. The individual fine flux trim rods are of the same neutron absorbing configuration as the individual rod cluster control units, and may comprise Ag-In-Cd absorbers clad with stainless steel.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US70012168A | 1968-01-24 | 1968-01-24 | |
US70025368A | 1968-01-24 | 1968-01-24 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1205731A true GB1205731A (en) | 1970-09-16 |
Family
ID=27106556
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB469/69A Expired GB1205731A (en) | 1968-01-24 | 1969-01-03 | Nuclear reactor control device |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE727295A (en) |
ES (1) | ES362484A1 (en) |
FR (1) | FR2000675A1 (en) |
GB (1) | GB1205731A (en) |
NL (1) | NL6901106A (en) |
SE (1) | SE358987B (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110603602A (en) * | 2017-05-09 | 2019-12-20 | 西屋电气有限责任公司 | Annular nuclear fuel pellet with discrete burnable absorber pins |
CN114188047A (en) * | 2021-12-03 | 2022-03-15 | 中国原子能科学研究院 | Reactivity control device |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4173513A (en) * | 1977-07-07 | 1979-11-06 | Westinghouse Electric Corp. | Nuclear reactor with control rods |
US4231843A (en) * | 1977-08-02 | 1980-11-04 | Westinghouse Electric Corp. | Guide tube flow diffuser |
US4550941A (en) * | 1980-12-16 | 1985-11-05 | Westinghouse Electric Corp. | Hydraulic drive mechanism |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2975119A (en) * | 1958-12-05 | 1961-03-14 | Clarence D Emmons | Vertical rod drive mechanism |
US3154472A (en) * | 1960-03-07 | 1964-10-27 | Bailey Meter Co | Rod drive for nuclear reactor |
FR1440906A (en) * | 1964-05-09 | 1966-06-03 | English Electric Co Ltd | Nuclear reactor and device for controlling its reactivity |
-
1969
- 1969-01-03 GB GB469/69A patent/GB1205731A/en not_active Expired
- 1969-01-14 ES ES362484A patent/ES362484A1/en not_active Expired
- 1969-01-23 BE BE727295D patent/BE727295A/xx unknown
- 1969-01-23 NL NL6901106A patent/NL6901106A/xx unknown
- 1969-01-24 FR FR6901354A patent/FR2000675A1/en active Granted
- 1969-01-24 SE SE01009/69A patent/SE358987B/xx unknown
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110603602A (en) * | 2017-05-09 | 2019-12-20 | 西屋电气有限责任公司 | Annular nuclear fuel pellet with discrete burnable absorber pins |
CN110603602B (en) * | 2017-05-09 | 2023-09-08 | 西屋电气有限责任公司 | Annular nuclear fuel pellets with discrete burnable absorber pins |
CN114188047A (en) * | 2021-12-03 | 2022-03-15 | 中国原子能科学研究院 | Reactivity control device |
CN114188047B (en) * | 2021-12-03 | 2024-05-14 | 中国原子能科学研究院 | Reactivity control device |
Also Published As
Publication number | Publication date |
---|---|
FR2000675B1 (en) | 1973-12-07 |
SE358987B (en) | 1973-08-13 |
NL6901106A (en) | 1969-07-28 |
ES362484A1 (en) | 1970-11-01 |
BE727295A (en) | 1969-07-23 |
FR2000675A1 (en) | 1969-09-12 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PLNP | Patent lapsed through nonpayment of renewal fees |