GB960678A - Nuclear power reactor with rod-shaped fuel elements - Google Patents
Nuclear power reactor with rod-shaped fuel elementsInfo
- Publication number
- GB960678A GB960678A GB39943/62A GB3994362A GB960678A GB 960678 A GB960678 A GB 960678A GB 39943/62 A GB39943/62 A GB 39943/62A GB 3994362 A GB3994362 A GB 3994362A GB 960678 A GB960678 A GB 960678A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reactor
- fuel
- ladder
- steam
- water
- 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
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
-
- 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
-
- 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
- G21C1/082—Reactors where the coolant is overheated
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
-
- 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)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
960,678. Reactors. BETEILIGUNGS-UND PATENTVERWALTUNGSGESELLSCHAFT. Oct. 22, 1962, No. 39943/62. Heading G6C. A nuclear reactor with no bottom grid has horizontally rod shaped fuel elements the ends of which are connected to longitudinal members to form a number of ladder-like groups in which the fuel elements form the rungs of the ladders. The invention is applicable to boiling water and gas cooled reactors and provides a single zone within the reactor in which superheating takes place. The fuel may be metallic or ceramic compounds of circular or elliptical cross-section. A further feature of all the embodiments described is that one of the longitudinal members of each "ladder" is movable in a direction parallel to the fuel element axes in order to accommodate thermal expansion. The water cooled reactor shown in Fig. 7 comprises two heating zones, the first heating the water, which may be heavy water acting as coolant, moderator and shield, and the second superheating the resultant steam. Each ladder-like fuel assembly is immersed in the liquid coolant, and the steam thereby generated accumulates above the water level in the reactor before passing into the first hollow longitudinal member 6 of the fuel assemblies From the member 6 the steam passes through the interiors of the hollow fuel elements 5, out through the second longitudinal member 7 and into a steam accumulator 8. Superheated steam passes from the accumulator either to a heat exchanger or direct to a turbine. The superheating coolant circuit may be modified by placing a divider at approximately the mid point of the longitudinal member 6, such that the entire steam flow passes from left to right in the upper half of the "ladder", and from right to left in the lower half. The upper end of the longitudinal member 7 is closed, and the steam accumulator is connected to the lower end of the member 6. In a modified form of boiling water reactor, solid fuel elements are used, there being no circulation of coolant within the "ladder". In this case, the superheating takes place in a zone above the water level into which the "ladder" ends project. The gas cooled reactor shown in Fig. 11 utilizes a solid fuel element surrounded by two spaced apart concentric graphite tubes (Figs. 8, 9, not shown). Provision is made for circulating a scavenging gas (entirely independent of the coolant circuit) through the graphite annulus surrounding each fuel element via inlet and outlet connections made to the two longitudinal members 24, 25. Gas . enters the reactor through an annulus 29 and passes dpward, cooling the reflector 28. The thus preheated gas then passes down through the core and out through a pipe 32. An advantageous feature of both the boiling water and gas cooled reactors described is that the "ladder" construction of the fuel assemblies obviates the need for a bottom grid plate. The weight of fuel is supported through the longitudinal members on an annular ring positioned in the bottom of the reactor.
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE624265D BE624265A (en) | 1962-10-22 | ||
GB39943/62A GB960678A (en) | 1962-10-22 | 1962-10-22 | Nuclear power reactor with rod-shaped fuel elements |
FR912979A FR1336626A (en) | 1962-10-22 | 1962-10-22 | Rod-shaped fuel element nuclear power reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB39943/62A GB960678A (en) | 1962-10-22 | 1962-10-22 | Nuclear power reactor with rod-shaped fuel elements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB960678A true GB960678A (en) | 1964-06-10 |
Family
ID=10412338
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB39943/62A Expired GB960678A (en) | 1962-10-22 | 1962-10-22 | Nuclear power reactor with rod-shaped fuel elements |
Country Status (2)
Country | Link |
---|---|
BE (1) | BE624265A (en) |
GB (1) | GB960678A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4343760A (en) * | 1979-11-14 | 1982-08-10 | The United States Of America As Represented By The United States Department Of Energy | Divertor target for magnetic containment device |
-
0
- BE BE624265D patent/BE624265A/xx unknown
-
1962
- 1962-10-22 GB GB39943/62A patent/GB960678A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4343760A (en) * | 1979-11-14 | 1982-08-10 | The United States Of America As Represented By The United States Department Of Energy | Divertor target for magnetic containment device |
Also Published As
Publication number | Publication date |
---|---|
BE624265A (en) |
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