ES246857A1 - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- ES246857A1 ES246857A1 ES0246857A ES246857A ES246857A1 ES 246857 A1 ES246857 A1 ES 246857A1 ES 0246857 A ES0246857 A ES 0246857A ES 246857 A ES246857 A ES 246857A ES 246857 A1 ES246857 A1 ES 246857A1
- Authority
- ES
- Spain
- Prior art keywords
- transverse
- coolant
- core
- flow
- fuel elements
- 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
- 239000002826 coolant Substances 0.000 abstract 3
- 239000000446 fuel Substances 0.000 abstract 3
- 239000000463 material Substances 0.000 abstract 2
- 230000000712 assembly Effects 0.000 abstract 1
- 238000000429 assembly Methods 0.000 abstract 1
- 230000005540 biological transmission Effects 0.000 abstract 1
- 239000000203 mixture Substances 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
-
- 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
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/02—Biological shielding ; Neutron or gamma shielding
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/04—Arrangements for expansion and contraction
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
-
- 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
- G21C7/00—Control of nuclear reaction
- G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
- G21C7/04—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Health & Medical Sciences (AREA)
- Biomedical Technology (AREA)
- General Health & Medical Sciences (AREA)
- Molecular Biology (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A nuclear reactor in which there is a core containing a mixture of fertirl material and fissile material, housed inside a pressure vessel between a coolant inlet chamber and a coolant outlet chamber, characterized in that the core includes a plurality of replaceable fuel element assemblies extending between a transverse inlet member and a transverse outlet member, each comprising a box or sleeve open at the ends that houses a plurality of enriched fuel elements, spaced and longitudinally extending, and is removably attached at the ends to said transverse members, so that the coolant coming from said inlet chamber can flow through the dunes in relation to heat exchange or transmission with the fuel elements housed in them, and can flow through the core in exchange or transm relationship heat ionisation with the outer surfaces of said covers. (Machine-translation by Google Translate, not legally binding)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US71251258A | 1958-01-31 | 1958-01-31 |
Publications (1)
Publication Number | Publication Date |
---|---|
ES246857A1 true ES246857A1 (en) | 1960-01-01 |
Family
ID=24862431
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES0246857A Expired ES246857A1 (en) | 1958-01-31 | 1959-01-28 | Improvements in or relating to nuclear reactors |
Country Status (4)
Country | Link |
---|---|
CH (1) | CH357812A (en) |
ES (1) | ES246857A1 (en) |
FR (1) | FR1228851A (en) |
GB (1) | GB913653A (en) |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
SE421969B (en) * | 1980-03-17 | 1982-02-08 | Asea Atom Ab | FUEL CARTRIDGE FOR A COOKING REACTOR |
US4514358A (en) * | 1981-03-31 | 1985-04-30 | Ab Asea-Atom | Fuel assembly |
SE431691B (en) * | 1982-07-12 | 1984-02-20 | Asea Atom Ab | KERNBRENSLEPATRON |
US4788033A (en) * | 1983-04-29 | 1988-11-29 | Westinghouse Electric Corp. | Calandria |
KR20090108709A (en) * | 2007-02-12 | 2009-10-16 | 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 | Pressurized water reactor flow skirt apparatus |
CN111916232B (en) * | 2020-08-13 | 2022-03-01 | 中国核动力研究设计院 | Light water nuclear reactor structure |
CN112185598B (en) * | 2020-09-30 | 2022-02-01 | 中国核动力研究设计院 | Stacking type flow distribution device and distribution structure |
-
1959
- 1959-01-27 GB GB2981/59A patent/GB913653A/en not_active Expired
- 1959-01-28 ES ES0246857A patent/ES246857A1/en not_active Expired
- 1959-01-30 CH CH357812D patent/CH357812A/en unknown
- 1959-01-31 FR FR785486A patent/FR1228851A/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
GB913653A (en) | 1962-12-19 |
FR1228851A (en) | 1960-09-02 |
CH357812A (en) | 1961-10-31 |
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