GB1064382A - Device for regulating the power of a nuclear reactor - Google Patents
Device for regulating the power of a nuclear reactorInfo
- Publication number
- GB1064382A GB1064382A GB24697/64A GB2469764A GB1064382A GB 1064382 A GB1064382 A GB 1064382A GB 24697/64 A GB24697/64 A GB 24697/64A GB 2469764 A GB2469764 A GB 2469764A GB 1064382 A GB1064382 A GB 1064382A
- Authority
- GB
- United Kingdom
- Prior art keywords
- container
- chain
- core
- channel
- control channel
- 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
-
- 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
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Particle Accelerators (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
Abstract
1,064,382. Reactor control rods. COMMISSARIAT A L'ENERGIE ATOMIQUE. June 15, 1964 [June 25, 1963; Oct. 30, 1963], No. 24697/64. Heading G6C. A neutron absorbing device in the form of a metal chain disposed in a vertical reactor channel has means for displacing it from a withdrawn position, in which it is entirely outside the core, to a deployed position in which it occupies substantially the entire height of the core, and is characterized in that in the withdrawn position it is housed in a detachable container aligned with the channel. The container may be above or below the core; and the chain or chains may be of stainless, boron or cadmium steel. The reactor is graphite moderated, and cooled by CO 2 . The control channel through the top reactor shield 4 has a tubular lining which contains three concrete filled metal plugs 10, 12, 14. Plug 10 houses a winch 24 for handling a cable 26 on which is suspended the absorbing device 90, in this case a plurality of chains 92. The plugs are removable, and are provided with handling grooves 44, 46, 48. Moderator column 58 is lined (62) to provide a control channel 64. The column 58 rests on a core support floor 74 to which is attached a housing 78 for the detachable chain container 84. Orifices 104, 106 are provided in the housing and container to allow coolant flow through both the container and the control channel. A gripping head 96 is fixed to the lower end of the hoist cable and is releasably attached to a chain head 94 by means of cam surfaces on the two heads arranged so that they automatically couple and uncouple (Fig. 4, not shown). To remove the neutron absorber, the chain head 94 is lowered until it rests in seating 98; the loss of tension in the cable releases the coupling and the gripping head 96 is withdrawn into a housing 38. The entire contents of the control channel may now be removed piece by piece (members 10, 12, 14, 66, 62, 86 and 84), and a new neutron absorber inserted. In a second embodiment (Figs. 5, 6, 7, not shown) the container is mounted above the core, and the neutron absorber comprises a single chain controlled by a meshing sprocket arranged above its container. The sprocket and associated driving means may be mounted in either a separate channel plug to that containing the chain container, or in the same plug. In this arrangement, the drive and neutron absorber may be replaced without removing shielding plugs situated below them, thus retaining partial shielding.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR939251A FR1368891A (en) | 1963-06-25 | 1963-06-25 | Device for regulating the power of a nuclear reactor |
| FR952351A FR84641E (en) | 1963-06-25 | 1963-10-30 | Device for regulating the power of a nuclear reactor |
| FR991268A FR86619E (en) | 1963-06-25 | 1964-10-13 | Device for regulating the power of a nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1064382A true GB1064382A (en) | 1967-04-05 |
Family
ID=27247303
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB24697/64A Expired GB1064382A (en) | 1963-06-25 | 1964-06-15 | Device for regulating the power of a nuclear reactor |
| GB41008/65A Expired GB1076708A (en) | 1963-06-25 | 1965-09-27 | Device for regulating the power level of a nuclear reactor |
Family Applications After (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB41008/65A Expired GB1076708A (en) | 1963-06-25 | 1965-09-27 | Device for regulating the power level of a nuclear reactor |
Country Status (8)
| Country | Link |
|---|---|
| BE (2) | BE649518A (en) |
| CH (1) | CH419362A (en) |
| DE (2) | DE1237234B (en) |
| FR (3) | FR1368891A (en) |
| GB (2) | GB1064382A (en) |
| LU (1) | LU46323A1 (en) |
| NL (2) | NL6407176A (en) |
| NO (2) | NO116095B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4019954A (en) * | 1974-11-07 | 1977-04-26 | Commissariat A L'energie Atomique | Safety device for a nuclear reactor and especially a fast reactor |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3438856A (en) * | 1967-12-29 | 1969-04-15 | Atomic Energy Commission | Nuclear reactor hydraulic control drive system |
| DE2058619C3 (en) * | 1970-11-28 | 1982-01-21 | Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach | Vertical control rod for quick and safe shutdown of nuclear reactors |
| RU2166214C1 (en) * | 2000-02-21 | 2001-04-27 | Государственный научный центр Российской Федерации Всероссийский научно-исследовательский институт неорганических материалов им. акад. А.А. Бочвара | Composite fuel assembly for power control system of nuclear reactor core |
| RU2190886C1 (en) * | 2001-10-31 | 2002-10-10 | Государственное предприятие "Московский завод полиметаллов" | Method for operating pressurized-tube uranium- graphite reactor and control element of pressurized-tube uranium-graphite reactor |
| RU2188470C1 (en) * | 2001-10-31 | 2002-08-27 | Государственное предприятие "Московский завод полиметаллов" | Control element of pressurized-tube uranium- graphite reactor |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE567089A (en) * | 1957-05-08 | 1900-01-01 | ||
| FR1188583A (en) * | 1957-11-12 | 1959-09-23 | Cie D Applic Et De Rech S Atom | Improvements to anti-reactivity control means for nuclear fission reactors and new products resulting from these improvements |
-
1963
- 1963-06-25 FR FR939251A patent/FR1368891A/en not_active Expired
- 1963-10-30 FR FR952351A patent/FR84641E/en not_active Expired
-
1964
- 1964-06-12 DE DEC33125A patent/DE1237234B/en active Pending
- 1964-06-15 LU LU46323D patent/LU46323A1/xx unknown
- 1964-06-15 GB GB24697/64A patent/GB1064382A/en not_active Expired
- 1964-06-16 CH CH781564A patent/CH419362A/en unknown
- 1964-06-19 BE BE649518A patent/BE649518A/xx unknown
- 1964-06-22 NO NO153760A patent/NO116095B/no unknown
- 1964-06-24 NL NL6407176A patent/NL6407176A/xx unknown
- 1964-10-13 FR FR991268A patent/FR86619E/en not_active Expired
-
1965
- 1965-09-27 GB GB41008/65A patent/GB1076708A/en not_active Expired
- 1965-09-27 BE BE670163D patent/BE670163A/xx unknown
- 1965-09-27 DE DEC36980A patent/DE1254778B/en active Pending
- 1965-09-30 NO NO159913A patent/NO116096B/no unknown
- 1965-10-13 NL NL6513241A patent/NL6513241A/xx unknown
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4019954A (en) * | 1974-11-07 | 1977-04-26 | Commissariat A L'energie Atomique | Safety device for a nuclear reactor and especially a fast reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| NO116096B (en) | 1969-01-27 |
| NL6407176A (en) | 1964-12-28 |
| FR86619E (en) | 1966-03-11 |
| NO116095B (en) | 1969-01-27 |
| LU46323A1 (en) | 1972-01-01 |
| NL6513241A (en) | 1966-04-14 |
| FR84641E (en) | 1965-03-19 |
| FR1368891A (en) | 1964-08-07 |
| DE1254778B (en) | 1967-11-23 |
| BE670163A (en) | 1966-01-17 |
| CH419362A (en) | 1966-08-31 |
| DE1237234B (en) | 1967-03-23 |
| BE649518A (en) | 1964-10-16 |
| GB1076708A (en) | 1967-07-19 |
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