GB1327196A - Safety devices for nuclear reactors - Google Patents
Safety devices for nuclear reactorsInfo
- Publication number
- GB1327196A GB1327196A GB5046369A GB1327196DA GB1327196A GB 1327196 A GB1327196 A GB 1327196A GB 5046369 A GB5046369 A GB 5046369A GB 1327196D A GB1327196D A GB 1327196DA GB 1327196 A GB1327196 A GB 1327196A
- Authority
- GB
- United Kingdom
- Prior art keywords
- rod
- strut
- reactor
- support tube
- pressure vessel
- 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
- 238000006073 displacement reaction Methods 0.000 abstract 3
- 238000004880 explosion Methods 0.000 abstract 1
- 230000005484 gravity Effects 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
- G21C9/04—Means for suppressing fires ; Earthquake protection
-
- 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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1327196 Controlling reactors REYROLLE PARSONS Ltd 6 Jan 1971 [14 Oct 1969] 50463/69 Heading G6C A reactor safety device operates automatically in response to a relative displacement between the reactor pressure vessel and the superstructure above it from which the control rods are suspended, for releasing the control rods to allow them to fall under gravity into the reactor core in response to the occurrence of a relative displacement in excess of a predetermined amount. In the embodiment shown, a control rod 10 is releasably latched within the lower end of a support tube 11 by means of three latch members 13 whose heads are held against a chamfered abutment 14 inside the support tube 11 by means of a conical end 15 on a plunger rod 16. The latch members 13 have cross-bars 13A at thier lower end which are engaged in an annular recess 10A beneath abutment surfaces in the head of the control rod 10. The rod 16 is biased upwardly by means of a spring 21 which bears against an abutment portion 22 of the rod 16 and a ring 23 biased within the support tube 11. The upper end of the rod 16 is tapered at 16A and has a flat end face 24 on which the conical end 25A of a detent strut 25 abuts. The upper end of the strut 25 is attached by a chain (not shown) to a motor-driven winch on a concrete superstructure above the pressure vessel. The strut 25 has a part-spherical intermediate portion 26 which bears against an inwardly tapering end cap 27 screwed to the top of support tube 11 and thus forms a fulcrum about which the strut 25 may move. Upon the occurrence of a displacement of the superstructure relative to the pressure vessel, caused for example by an earthquake, an explosion in the vicinity of the reactor or a structural fault in some part of the reactor, a tilting of the strut 25 will occur about the fulcrum 26 causing its conical end 25A to move across the face 24 of the plunger rod 16. Should the tilting exceed a predetermined amount, e.g. 2 degrees, the end 25A will move beyond the edge of the face 24 and the rod 16 will be driven upwards by the spring 21 thus releasing the latch members 13 and allowing the control rod 10 to fall into the reactor core.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB5046369 | 1969-10-14 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1327196A true GB1327196A (en) | 1973-08-15 |
Family
ID=10455984
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB5046369A Expired GB1327196A (en) | 1969-10-14 | 1969-10-14 | Safety devices for nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1327196A (en) |
Cited By (3)
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 |
CN108922638A (en) * | 2018-07-25 | 2018-11-30 | 中广核研究院有限公司 | A kind of control rod drive mechanism with auxiliary scram device |
CN111916228A (en) * | 2020-07-31 | 2020-11-10 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Drive rod group on control rod drive mechanism and offshore reactor |
-
1969
- 1969-10-14 GB GB5046369A patent/GB1327196A/en not_active Expired
Cited By (5)
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 |
CN108922638A (en) * | 2018-07-25 | 2018-11-30 | 中广核研究院有限公司 | A kind of control rod drive mechanism with auxiliary scram device |
CN108922638B (en) * | 2018-07-25 | 2024-05-17 | 中广核研究院有限公司 | Control rod driving mechanism with auxiliary rod falling device |
CN111916228A (en) * | 2020-07-31 | 2020-11-10 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Drive rod group on control rod drive mechanism and offshore reactor |
CN111916228B (en) * | 2020-07-31 | 2023-06-06 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Driving rod group on control rod driving mechanism and offshore reactor |
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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 |