GB1309883A - Nuclear reactors - Google Patents
Nuclear reactorsInfo
- Publication number
- GB1309883A GB1309883A GB725571*[A GB1309883DA GB1309883A GB 1309883 A GB1309883 A GB 1309883A GB 1309883D A GB1309883D A GB 1309883DA GB 1309883 A GB1309883 A GB 1309883A
- Authority
- GB
- United Kingdom
- Prior art keywords
- heat
- transfer medium
- fuel
- heat exchanger
- 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- 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
- G21C1/10—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 moderator and coolant being different or separated
- G21C1/12—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 moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/26—Control of nuclear reaction by displacement of the moderator or parts thereof by changing the moderator concentration
-
- 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)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
1309883 Nuclear reactors UNITED KING- DOM ATOMIC ENERGY AUTHORITY 3 March 1972 [18 March 1971] 7255/71 Heading G6C In a nuclear reactor construction, heat is transferred from the nuclear fuel to heat energy conversion apparatus by use of a finely-divided solid material as a heat transfer medium. In one form, the heat-transfer medium, which also acts as moderator falls from the reactor vessel on to a heat exchanger under the influence of gravity; the flow may be regulated by a valve. In another form, in which the heat exchanger is remote from the vessel, the heattransfer medium is conveyed to above the heat exchanger by conveyer. The heat-transfer medium is returned to above the fuel by conveyer. The heat-transfer medium may be finely-divided graphite, and may be maintained in a free flowing condition by vibrating or pulsating means. Reactivity in the core can be varied by raising and lowering the fuel elements. Emergency shut-down is effected by injecting neutronabsorbing material into containers penetrating the graphite mass. The fuel elements may be sheathed, or may comprise fission-product retaining particles in a matrix which has no sheath. An inert covered gas may be used in the system. Where the construction is to be used for generating electricity, power cylcing of the reactor is reduced by storing hot cooling and moderating material during periods of low heat energy consumption.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB725571 | 1971-03-18 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1309883A true GB1309883A (en) | 1973-03-14 |
Family
ID=9829611
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB725571*[A Expired GB1309883A (en) | 1971-03-18 | 1971-03-18 | Nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1309883A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2008005590A2 (en) * | 2006-02-22 | 2008-01-10 | University Of Florida Research Foundation, Inc. | Nuclear reactor having efficient and highly stable thermal transfer fluid |
WO2014015740A1 (en) * | 2012-07-25 | 2014-01-30 | Li Zhengwei | Spherical fuel reactor |
-
1971
- 1971-03-18 GB GB725571*[A patent/GB1309883A/en not_active Expired
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2008005590A2 (en) * | 2006-02-22 | 2008-01-10 | University Of Florida Research Foundation, Inc. | Nuclear reactor having efficient and highly stable thermal transfer fluid |
WO2008005590A3 (en) * | 2006-02-22 | 2008-03-06 | Univ Florida | Nuclear reactor having efficient and highly stable thermal transfer fluid |
US8731133B2 (en) | 2006-02-22 | 2014-05-20 | University of Florida Research Institute Foundation, Inc. | Nuclear reactor having efficient and highly stable thermal transfer fluid |
US10037824B2 (en) | 2006-02-22 | 2018-07-31 | University Of Florida Research Foundation, Inc. | Nuclear reactor having efficient and highly stable carbon-based thermal transfer fluid |
WO2014015740A1 (en) * | 2012-07-25 | 2014-01-30 | Li Zhengwei | Spherical fuel reactor |
GB2518991A (en) * | 2012-07-25 | 2015-04-08 | Zhengwei Li | Spherical fuel reactor |
GB2518991B (en) * | 2012-07-25 | 2018-06-06 | Li Zhengwei | Spherical fuel reactor |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PLNP | Patent lapsed through nonpayment of renewal fees |