DE1223466B - Brennstoffelementbuendel fuer bei hoher Temperatur betriebene gasgekuehlte Kernreaktoren - Google Patents
Brennstoffelementbuendel fuer bei hoher Temperatur betriebene gasgekuehlte KernreaktorenInfo
- Publication number
- DE1223466B DE1223466B DEU10271A DEU0010271A DE1223466B DE 1223466 B DE1223466 B DE 1223466B DE U10271 A DEU10271 A DE U10271A DE U0010271 A DEU0010271 A DE U0010271A DE 1223466 B DE1223466 B DE 1223466B
- Authority
- DE
- Germany
- Prior art keywords
- components
- fuel element
- bundle
- gas
- leg
- 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.)
- Pending
Links
- 239000000446 fuel Substances 0.000 title claims description 16
- 239000000306 component Substances 0.000 claims description 22
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 21
- 229910002804 graphite Inorganic materials 0.000 claims description 21
- 239000010439 graphite Substances 0.000 claims description 21
- 210000002414 leg Anatomy 0.000 claims description 17
- 210000000689 upper leg Anatomy 0.000 claims description 13
- 239000000463 material Substances 0.000 claims description 9
- 239000008358 core component Substances 0.000 claims description 7
- 239000000112 cooling gas Substances 0.000 claims description 2
- 238000005260 corrosion Methods 0.000 claims description 2
- 230000007797 corrosion Effects 0.000 claims description 2
- 239000008240 homogeneous mixture Substances 0.000 claims description 2
- 229910052751 metal Inorganic materials 0.000 claims description 2
- 239000002184 metal Substances 0.000 claims description 2
- 239000003758 nuclear fuel Substances 0.000 claims description 2
- 239000002826 coolant Substances 0.000 description 7
- 229910001220 stainless steel Inorganic materials 0.000 description 4
- 239000010935 stainless steel Substances 0.000 description 4
- 238000001816 cooling Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 241000239290 Araneae Species 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 239000011258 core-shell material Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
-
- 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
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
-
- 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
-
- 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
- G21C3/041—Means for removal of gases from fuel elements
-
- 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
- G21C3/16—Details of the construction within the casing
- G21C3/18—Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
-
- 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
- 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
- G21C3/3213—Means for the storage or removal of fission gases
-
- 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
- G21C5/16—Shape of its constituent parts
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB36775/56A GB850015A (en) | 1956-11-30 | 1956-11-30 | Improvements in or relating to fuel elements for nuclear reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1223466B true DE1223466B (de) | 1966-08-25 |
Family
ID=10391090
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEU10271A Pending DE1223466B (de) | 1956-11-30 | 1957-11-30 | Brennstoffelementbuendel fuer bei hoher Temperatur betriebene gasgekuehlte Kernreaktoren |
| DEU4969A Pending DE1175804B (de) | 1956-11-30 | 1957-11-30 | Brennstoffelement fuer gasgekuehlte Kernreaktoren |
Family Applications After (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEU4969A Pending DE1175804B (de) | 1956-11-30 | 1957-11-30 | Brennstoffelement fuer gasgekuehlte Kernreaktoren |
Country Status (6)
| Country | Link |
|---|---|
| BE (1) | BE562864A (en:Method) |
| CH (1) | CH360137A (en:Method) |
| DE (2) | DE1223466B (en:Method) |
| FR (2) | FR1187404A (en:Method) |
| GB (1) | GB850015A (en:Method) |
| NL (3) | NL6503923A (en:Method) |
Families Citing this family (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE581046A (en:Method) * | 1958-07-25 | 1900-01-01 | ||
| BE591447A (en:Method) * | 1959-06-03 | |||
| US3182001A (en) * | 1959-07-23 | 1965-05-04 | Siemens Ag | Heterogeneous nuclear reactor |
| US3146173A (en) * | 1960-03-07 | 1964-08-25 | Fortescue Peter | Fuel element |
| NL255838A (en:Method) * | 1960-03-07 | |||
| US3141829A (en) * | 1960-04-19 | 1964-07-21 | Fortescue Peter | Fuel element |
| US3128234A (en) * | 1960-08-26 | 1964-04-07 | Jr Joseph F Cage | Modular core units for a neutronic reactor |
| NL272289A (en:Method) * | 1960-12-09 | |||
| US3114693A (en) * | 1961-07-12 | 1963-12-17 | William T Furgerson | Vented fuel element for gas-cooled neutronic reactors |
| NL281237A (en:Method) * | 1961-07-31 | |||
| BE620998A (en:Method) * | 1961-08-02 | 1900-01-01 | ||
| BE624769A (en:Method) * | 1961-11-15 | 1900-01-01 | ||
| NL290809A (en:Method) * | 1962-03-28 | 1900-01-01 | ||
| DE1237231B (de) * | 1963-02-08 | 1967-03-23 | Kernforschung Mit Beschraenkte | Spanneinrichtung fuer die Spalt- und Brutzone eines Atomkernreaktors |
| FR1544171A (fr) * | 1967-09-20 | 1968-10-31 | Creusot Forges Ateliers | Réacteur nucléaire fonctionnant à haute température |
| DE4218023A1 (de) * | 1992-06-01 | 1993-12-02 | Siemens Ag | Brennstab eines Kernreaktors |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH286658A (de) * | 1950-11-09 | 1952-10-31 | Sulzer Ag | Verfahren zum Nutzbarmachen von Atomenergie und Atomreaktor zum Durchführen des Verfahrens. |
| GB754183A (en) * | 1954-05-14 | 1956-08-01 | Asea Ab | Improvements in nuclear-chain reactors |
-
0
- NL NL222873D patent/NL222873A/xx unknown
- NL NL128573D patent/NL128573C/xx active
- BE BE562864D patent/BE562864A/xx unknown
-
1956
- 1956-11-30 GB GB36775/56A patent/GB850015A/en not_active Expired
-
1957
- 1957-11-30 DE DEU10271A patent/DE1223466B/de active Pending
- 1957-11-30 CH CH360137D patent/CH360137A/de unknown
- 1957-11-30 DE DEU4969A patent/DE1175804B/de active Pending
- 1957-11-30 FR FR1187404D patent/FR1187404A/fr not_active Expired
- 1957-11-30 FR FR1187405D patent/FR1187405A/fr not_active Expired
-
1965
- 1965-03-26 NL NL6503923A patent/NL6503923A/xx unknown
Non-Patent Citations (1)
| Title |
|---|
| None * |
Also Published As
| Publication number | Publication date |
|---|---|
| FR1187404A (fr) | 1959-09-10 |
| GB850015A (en) | 1960-09-28 |
| NL222873A (en:Method) | |
| NL128573C (en:Method) | |
| CH360137A (de) | 1962-02-15 |
| NL6503923A (en:Method) | 1965-05-25 |
| FR1187405A (fr) | 1959-09-10 |
| BE562864A (en:Method) | |
| DE1175804B (de) | 1964-08-13 |
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