GB905684A - Improvements relating to pressure vessels - Google Patents
Improvements relating to pressure vesselsInfo
- Publication number
- GB905684A GB905684A GB23258/60A GB2325860A GB905684A GB 905684 A GB905684 A GB 905684A GB 23258/60 A GB23258/60 A GB 23258/60A GB 2325860 A GB2325860 A GB 2325860A GB 905684 A GB905684 A GB 905684A
- Authority
- GB
- United Kingdom
- Prior art keywords
- pressure
- disc
- atmospheric side
- fire
- reactor
- 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
- 239000000446 fuel Substances 0.000 abstract 3
- 239000002826 coolant Substances 0.000 abstract 2
- 238000002347 injection Methods 0.000 abstract 2
- 239000007924 injection Substances 0.000 abstract 2
- 239000012528 membrane Substances 0.000 abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 2
- 230000009172 bursting Effects 0.000 abstract 1
- 239000012530 fluid Substances 0.000 abstract 1
- 239000002184 metal Substances 0.000 abstract 1
- 230000001629 suppression 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
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
-
- 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
- G21C9/004—Pressure suppression
- G21C9/008—Pressure suppression by rupture-discs or -diaphragms
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
905,684. Reactor pressure vessels. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. July 4, 1961 [July 4, 1960], No. 23258/60. Class 39 (4). Fire suppression in a nuclear reactor is effected by the injection of a fire-suppressing fluid into the fuel channels through the piping system used to monitor the coolant to detect fuel element sheathing failure. The coolant from each channel passes through a detector and then into a common return duct from which it is pumped back into the pressure vessel. A valve 23, Fig. 2, is incorporated in the return duct and comprises an impervious membrane 24 in the form of a bursting disc and a perforated metal support backing 25 at the atmospheric side of 24. A small pressure differential acting from the atmospheric side, i.e. from left to right will fracture disc 24 while the disc, supported by the backing 25 resists the normal pressure within the reactor. If the pressure vessel is ruptured and a fall of internal pressure results, a fuel fire is prevented by the injection of borated water through valve 23 from the atmospheric side, the membrane 24 being broken by the low water pressure.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB23258/60A GB905684A (en) | 1960-07-04 | 1960-07-04 | Improvements relating to pressure vessels |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB23258/60A GB905684A (en) | 1960-07-04 | 1960-07-04 | Improvements relating to pressure vessels |
Publications (1)
Publication Number | Publication Date |
---|---|
GB905684A true GB905684A (en) | 1962-09-12 |
Family
ID=10192730
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB23258/60A Expired GB905684A (en) | 1960-07-04 | 1960-07-04 | Improvements relating to pressure vessels |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB905684A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3207672A (en) * | 1962-08-07 | 1965-09-21 | Commissariat Energie Atomique | Fire extinguishing system for nuclear reactors |
US3232843A (en) * | 1963-02-26 | 1966-02-01 | Reactor Centrum Nederland | Containment system for a plurality of nuclear reactor units |
CN113972017A (en) * | 2021-10-22 | 2022-01-25 | 中国原子能科学研究院 | Ionization chamber channel |
-
1960
- 1960-07-04 GB GB23258/60A patent/GB905684A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3207672A (en) * | 1962-08-07 | 1965-09-21 | Commissariat Energie Atomique | Fire extinguishing system for nuclear reactors |
US3232843A (en) * | 1963-02-26 | 1966-02-01 | Reactor Centrum Nederland | Containment system for a plurality of nuclear reactor units |
CN113972017A (en) * | 2021-10-22 | 2022-01-25 | 中国原子能科学研究院 | Ionization chamber channel |
CN113972017B (en) * | 2021-10-22 | 2024-05-10 | 中国原子能科学研究院 | Ionization chamber channel |
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