GB1236578A - Nuclear reactor installations - Google Patents
Nuclear reactor installationsInfo
- Publication number
- GB1236578A GB1236578A GB54370/67A GB5437067A GB1236578A GB 1236578 A GB1236578 A GB 1236578A GB 54370/67 A GB54370/67 A GB 54370/67A GB 5437067 A GB5437067 A GB 5437067A GB 1236578 A GB1236578 A GB 1236578A
- Authority
- GB
- United Kingdom
- Prior art keywords
- core
- nov
- pressure vessel
- coolant circuit
- moderator
- 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
- 238000009434 installation Methods 0.000 title 1
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 abstract 2
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 abstract 2
- 239000002826 coolant Substances 0.000 abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 2
- 238000009835 boiling Methods 0.000 abstract 1
- 229910002092 carbon dioxide Inorganic materials 0.000 abstract 1
- 239000001569 carbon dioxide Substances 0.000 abstract 1
- 238000001816 cooling Methods 0.000 abstract 1
- 239000000446 fuel Substances 0.000 abstract 1
- 230000009257 reactivity 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1,236,578. Cooling reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 14 Nov., 1968 [29 Nov., 1967], No. 54370/67. Heading G6C. The reactor core 1 is cooled by the circulation of boiling water upwards through the vertical fuel tubes 4 mounted within a heavy water moderator contained in a Calandria tank. The coolant circuit 2 and core 1 are mounted within the concrete pressure vessel 3 which has an atmosphere of pressurized carbon dioxide gas. The gas and water pressures are substantially the same and thus a large fracture of the coolant circuit is unlikely. Depressurization of the pressure vessel causes ejection of plugs from the Calandria and the flashing off of steam from the moderator thereby reducing moderation and core reactivity.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB54370/67A GB1236578A (en) | 1967-11-29 | 1967-11-29 | Nuclear reactor installations |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB54370/67A GB1236578A (en) | 1967-11-29 | 1967-11-29 | Nuclear reactor installations |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1236578A true GB1236578A (en) | 1971-06-23 |
Family
ID=10470784
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB54370/67A Expired GB1236578A (en) | 1967-11-29 | 1967-11-29 | Nuclear reactor installations |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1236578A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4986956A (en) * | 1989-11-27 | 1991-01-22 | Stone & Webster Engineering Corporation | Passive nuclear power plant containment system |
-
1967
- 1967-11-29 GB GB54370/67A patent/GB1236578A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4986956A (en) * | 1989-11-27 | 1991-01-22 | Stone & Webster Engineering Corporation | Passive nuclear power plant containment system |
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