GB1102137A - Fuel element for nuclear superheat reactor - Google Patents
Fuel element for nuclear superheat reactorInfo
- Publication number
- GB1102137A GB1102137A GB22964/66A GB2296466A GB1102137A GB 1102137 A GB1102137 A GB 1102137A GB 22964/66 A GB22964/66 A GB 22964/66A GB 2296466 A GB2296466 A GB 2296466A GB 1102137 A GB1102137 A GB 1102137A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- process tube
- burnable poison
- fertile
- fertile material
- 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
- 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)
- Physical Or Chemical Processes And Apparatus (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,102,137. Fuel elements. HITACHI Ltd. 23 May, 1966 [24 May, 1965; 11 June, 1965], No. 22964/66. Heading G6C. A fuel element for a nuclear superheat reactor comprises fuel material and a process tube surrounding and spaced from the fuel material to provide a coolant passage, the process tube being made at least in part from a fertile material and/or a burnable poison whose fissile material content is lower than that of the fuel material, the process tube providing thermal insulation between water vapour coolant passing through the passage and a moderator. The fertile material may be depleted uranium oxide or natural uranium oxide or their mixtures, while the burnable poison may be boron carbide, europium or dysprosium. The addition of a very small amount of burnable poison to the process tube is sufficient to compensate for the fuel burn-up, whereas the addition of fertile material is never fully sufficient for this purpose. However, process tubes containing fertile material in producing fissile material are highly useful from the viewpoint of neutron economy.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3023165 | 1965-05-24 | ||
JP3438265 | 1965-06-11 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1102137A true GB1102137A (en) | 1968-02-07 |
Family
ID=26368542
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB22964/66A Expired GB1102137A (en) | 1965-05-24 | 1966-05-23 | Fuel element for nuclear superheat reactor |
Country Status (2)
Country | Link |
---|---|
DE (1) | DE1564078A1 (en) |
GB (1) | GB1102137A (en) |
-
1966
- 1966-05-23 GB GB22964/66A patent/GB1102137A/en not_active Expired
- 1966-05-24 DE DE19661564078 patent/DE1564078A1/en active Pending
Also Published As
Publication number | Publication date |
---|---|
DE1564078A1 (en) | 1970-02-19 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB852293A (en) | Improvements in boiling reactors | |
GB807817A (en) | Fuel-breeder fuel element for nuclear reactor | |
GB834371A (en) | High flux homogeneous nuclear process and reactor with circulating fissile material | |
GB1191806A (en) | Single Fluid Molten Salt Nuclear Breeder Reactor | |
GB840740A (en) | A steam stirred homogeneous nuclear reactor | |
GB852366A (en) | Nuclear reactor including a package safety device | |
GB1062247A (en) | Long lifetime nuclear reactor | |
GB1245757A (en) | Improvements in or relating to nuclear reactors | |
GB1128826A (en) | Fuel assembly for a nuclear reactor cooled by a liquid metal | |
GB1061274A (en) | Improvements in nuclear reactors and a method of operating same | |
GB1060999A (en) | Liquid metal fast breeder reactor | |
GB1002273A (en) | Fast reactor core | |
GB1209632A (en) | Improvements in or relating to nuclear reactors | |
GB1102137A (en) | Fuel element for nuclear superheat reactor | |
GB1299038A (en) | Fast reactor | |
GB1067136A (en) | Thermal neutron reactor | |
GB903489A (en) | Improvements in or relating to core elements for nuclear reactors | |
GB1056950A (en) | Control elements for fast nuclear reactors | |
GB958088A (en) | Improvements in or relating to fast nuclear reactors | |
GB1077385A (en) | An improved method of operating a nuclear reactor | |
GB1138288A (en) | Method of flux separation in nuclear reactors and structure therefor | |
GB1482991A (en) | Nuclear reactor and process for production of nuclear fue | |
GB1236331A (en) | Pressure tube type fuel assembly for nuclear reactor | |
KR100237136B1 (en) | Candu fuel bundle with a low void coefficient | |
GB898712A (en) | Nuclear reactor fuel element |