GB1201694A - A safety device for a nuclear reactor - Google Patents
A safety device for a nuclear reactorInfo
- Publication number
- GB1201694A GB1201694A GB39379/68A GB3937968A GB1201694A GB 1201694 A GB1201694 A GB 1201694A GB 39379/68 A GB39379/68 A GB 39379/68A GB 3937968 A GB3937968 A GB 3937968A GB 1201694 A GB1201694 A GB 1201694A
- Authority
- GB
- United Kingdom
- Prior art keywords
- rod
- stem
- rings
- punch
- braking
- 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
- 230000002745 absorbent Effects 0.000 abstract 1
- 239000002250 absorbent Substances 0.000 abstract 1
- 238000013459 approach Methods 0.000 abstract 1
- 230000008878 coupling Effects 0.000 abstract 1
- 238000010168 coupling process Methods 0.000 abstract 1
- 238000005859 coupling reaction Methods 0.000 abstract 1
- 238000010304 firing Methods 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/024—Rupture diaphragms
-
- 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
- G21C7/20—Disposition of shock-absorbing devices ; Braking arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Vibration Dampers (AREA)
- Magnetic Resonance Imaging Apparatus (AREA)
Abstract
1,201,694. Energy-absorbing devices. COMMISSARIAT A L'ENERGIE ATOMIQUE. 16 Aug., 1968 [18 Aug., 1967], No. 39379/68. Heading F2E. [Also in Division G6] A safety device for a nuclear reactor comprises an absorbent rod movable axially in a horizontal channel, means for propelling the rod in the channel to bring it to a position leading to shut-down of the reactor, a stem coaxial with the rod and along which the rod is slidable, the stem having at its forward end an end portion for braking and stopping the rod at the end of its stroke, an annular punch slidable along the stem between a position intermediate the ends of the stem and a position adjacent the braking end portion, and a series of rings attached to the rod and deformable by the punch as the rod approaches the end of its stroke. In the embodiment described, the rod 2 is propelled by means of a detachable propeller 12 (shown in Fig. 1) situated in a fixed ferrule 13 inside a tube 4 which forms an extension of a horizontal channel in the reactor moderator. The propeller 12 comprises a pressurized-gas chamber 15 closed by a diaphragm 16. By means of a firing pin 17, operated by a pyrotechnic device, the diaphragm 16 can be caused to rupture so that the gas escapes under pressure along the ferrule 13 to the rod 2. An extension 18 on the propeller unit is attached by means of a stud and slot coupling 23 to a gripping socket 20 on the rear end of a stem 6 upon which the rod 2 slides. Braking of the rod 2 is effected by the deformation of rings 10 (Fig. 4) provided on the interior of the rear end of the rod 2. The internal diameter of these rings is less than that of the rod. They are deformed by an annular punch 11 which, before operation, is held at the front end of the rod 2. The punch 11 is slidable on the stem 6 and when the rod 2 is propelled into the reactor core, the punch 11 comes to bear on the end portion 8 of the stem 6 and then slides inside the rod 2 as far as the braking rings 10. The deformation of these rings absorbs the kinetic energy of the rod.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR118359A FR1541063A (en) | 1967-08-18 | 1967-08-18 | Safety device for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1201694A true GB1201694A (en) | 1970-08-12 |
Family
ID=8637088
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB39379/68A Expired GB1201694A (en) | 1967-08-18 | 1968-08-16 | A safety device for a nuclear reactor |
Country Status (2)
| Country | Link |
|---|---|
| FR (1) | FR1541063A (en) |
| GB (1) | GB1201694A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4687621A (en) * | 1984-08-06 | 1987-08-18 | Westinghouse Electric Corp. | Nuclear fuel assembly with improved spectral shift-producing rods |
-
1967
- 1967-08-18 FR FR118359A patent/FR1541063A/en not_active Expired
-
1968
- 1968-08-16 GB GB39379/68A patent/GB1201694A/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| FR1541063A (en) | 1968-10-04 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| CSNS | Application of which complete specification have been accepted and published, but patent is not sealed |