GB1026845A - A fuel-rod assembly for liquid-cooled nuclear reactors - Google Patents
A fuel-rod assembly for liquid-cooled nuclear reactorsInfo
- Publication number
- GB1026845A GB1026845A GB4822/63A GB482263A GB1026845A GB 1026845 A GB1026845 A GB 1026845A GB 4822/63 A GB4822/63 A GB 4822/63A GB 482263 A GB482263 A GB 482263A GB 1026845 A GB1026845 A GB 1026845A
- Authority
- GB
- United Kingdom
- Prior art keywords
- water
- fuel
- valve
- reactor
- rods
- 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
- G21C1/08—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
-
- 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
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
-
- 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
-
- 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
1,026,845. Reactors. LICENTIA PATENTVERWALTUNGS-G.m.b.H. Feb. 6, 1963 [Feb. 6, 1962; Jan. 30, 1963], No. 4822/63. Heading G6C. A fuel element (Figs. 1a, 1b, not shown) comprising fuel rods 6 disposed within an annular channel 5 between coaxial tubes 4, 7 has a number of baffles 12 disposed helically round its longitudinal axis and provided with bores to receive the rods 6 so that coolant flowing through the channel 5 has a transverse as well as a longitudinal component of flow. This overcomes the disadvantage with pure longitudinal flow that the coolant has a higher temperature adjacent the fuel rods which lie towards the centre of the core than adjacent those situated towards the edge of the core. In a light watercooled and moderated reactor employing fuel elements of this construction (Fig. 2, not shown) the water enters through a valve 28 at about 300‹ C. and is divided equally between an upper distributer ring 20 and a lower distributer system 16. From the latter, the water flows up supply tubes 11 housed within inner moderator compartments 10 of the fuel elements to be deflected by the closed ends of inner casing tubes 9 down through the compartments 10 whence it rises outside outer casing tubes 2 through an outer moderator compartment 1 to flow laterally through a gap formed between a fuel element support grid 17 and a dividing plate 18 into a compartment 19 where it mixes with the water from the distributer ring 20. The water subsequently flows up through the channels 5 where it is preheated to critical temperature and then superheated to 600‹ C. The superheated steam is collected in an insulated dome 21 above the grid 17 and supplied to a turbine through an insulated conduit 24. The necessary pressure drop for the flow through the channels 5 is produced by a cushion of pressure gas 27 above the free surface 26 of the water, the pressure of which is regulated by a valve 33 and regulator 37 connected by a conduit 32 to a gas container 31, excess gas being released through a valve 38. The temperature of the superheated steam, measured by means of a temperature detector 30, is used to adjust the setting of control rods 29. Since, however, this adjustmen involves a few seconds delay, the control rods must be preliminarily adjusted directly by the turbine, the generator or the mains on variations in load and the temperature used only for fine adjustment. The water level in the reactor pressure vessel 14 is maintained constant by means of an automatic regulator 39. Emergency shut-down of the reactor is effected by forcing gas from the container 31 through a valve 35 in a conduit 34 into the distributer system 16 to displace the water from the moderator compartments 10 and the supply tubes 11, thus rendering the reactor sub-critical.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DEL41137A DE1279858B (en) | 1962-02-06 | 1962-02-06 | Nuclear reactor fuel assembly |
DEL0044013 | 1963-01-30 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1026845A true GB1026845A (en) | 1966-04-20 |
Family
ID=25985504
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB4822/63A Expired GB1026845A (en) | 1962-02-06 | 1963-02-06 | A fuel-rod assembly for liquid-cooled nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1026845A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0544506A1 (en) * | 1991-11-27 | 1993-06-02 | General Electric Company | Nuclear reactor with low-level core coolant intake |
DE102005008848A1 (en) * | 2005-02-26 | 2006-08-31 | Forschungszentrum Karlsruhe Gmbh | Nuclear reactor fuel element, comprises parallel fuel rods enclosed in a casing which has inner and outer walls |
-
1963
- 1963-02-06 GB GB4822/63A patent/GB1026845A/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0544506A1 (en) * | 1991-11-27 | 1993-06-02 | General Electric Company | Nuclear reactor with low-level core coolant intake |
DE102005008848A1 (en) * | 2005-02-26 | 2006-08-31 | Forschungszentrum Karlsruhe Gmbh | Nuclear reactor fuel element, comprises parallel fuel rods enclosed in a casing which has inner and outer walls |
DE102005008848B4 (en) * | 2005-02-26 | 2007-03-22 | Forschungszentrum Karlsruhe Gmbh | Fuel assembly and fuel bundle for nuclear reactor with supercritical water |
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