DE1175804B - Brennstoffelement fuer gasgekuehlte Kernreaktoren - Google Patents
Brennstoffelement fuer gasgekuehlte KernreaktorenInfo
- Publication number
- DE1175804B DE1175804B DEU4969A DEU0004969A DE1175804B DE 1175804 B DE1175804 B DE 1175804B DE U4969 A DEU4969 A DE U4969A DE U0004969 A DEU0004969 A DE U0004969A DE 1175804 B DE1175804 B DE 1175804B
- Authority
- DE
- Germany
- Prior art keywords
- rod
- fuel
- fuel element
- gas
- moderator
- 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 18
- 239000000463 material Substances 0.000 claims description 13
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 9
- 229910002804 graphite Inorganic materials 0.000 description 9
- 239000010439 graphite Substances 0.000 description 9
- 239000003758 nuclear fuel Substances 0.000 description 9
- 239000008358 core component Substances 0.000 description 3
- 230000001681 protective effect Effects 0.000 description 3
- 125000006850 spacer group Chemical group 0.000 description 3
- 239000000306 component Substances 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 238000009395 breeding Methods 0.000 description 1
- 230000001488 breeding effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000005553 drilling Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 239000011796 hollow space material Substances 0.000 description 1
- 239000011872 intimate mixture Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 210000000689 upper leg Anatomy 0.000 description 1
- 229910052726 zirconium Inorganic materials 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 |
---|---|
DE1175804B true DE1175804B (de) | 1964-08-13 |
Family
ID=10391090
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DEU4969A Pending DE1175804B (de) | 1956-11-30 | 1957-11-30 | Brennstoffelement fuer gasgekuehlte Kernreaktoren |
DEU10271A Pending DE1223466B (de) | 1956-11-30 | 1957-11-30 | Brennstoffelementbuendel fuer bei hoher Temperatur betriebene gasgekuehlte Kernreaktoren |
Family Applications After (1)
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 |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE562864A (enrdf_load_stackoverflow) |
CH (1) | CH360137A (enrdf_load_stackoverflow) |
DE (2) | DE1175804B (enrdf_load_stackoverflow) |
FR (2) | FR1187404A (enrdf_load_stackoverflow) |
GB (1) | GB850015A (enrdf_load_stackoverflow) |
NL (3) | NL6503923A (enrdf_load_stackoverflow) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE4218023A1 (de) * | 1992-06-01 | 1993-12-02 | Siemens Ag | Brennstab eines Kernreaktors |
Families Citing this family (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3172820A (en) * | 1958-07-25 | 1965-03-09 | Neutronic reactor | |
BE591447A (enrdf_load_stackoverflow) * | 1959-06-03 | |||
US3182001A (en) * | 1959-07-23 | 1965-05-04 | Siemens Ag | Heterogeneous nuclear reactor |
NL255838A (enrdf_load_stackoverflow) * | 1960-03-07 | |||
US3141829A (en) * | 1960-04-19 | 1964-07-21 | Fortescue Peter | Fuel element |
US3146173A (en) * | 1960-03-07 | 1964-08-25 | Fortescue Peter | Fuel element |
US3128234A (en) * | 1960-08-26 | 1964-04-07 | Jr Joseph F Cage | Modular core units for a neutronic reactor |
NL272289A (enrdf_load_stackoverflow) * | 1960-12-09 | |||
US3114693A (en) * | 1961-07-12 | 1963-12-17 | William T Furgerson | Vented fuel element for gas-cooled neutronic reactors |
NL281237A (enrdf_load_stackoverflow) * | 1961-07-31 | |||
NL281596A (enrdf_load_stackoverflow) * | 1961-08-02 | 1900-01-01 | ||
BE624769A (enrdf_load_stackoverflow) * | 1961-11-15 | 1900-01-01 | ||
BE630217A (enrdf_load_stackoverflow) * | 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 |
Citations (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
- BE BE562864D patent/BE562864A/xx unknown
- NL NL222873D patent/NL222873A/xx unknown
- NL NL128573D patent/NL128573C/xx active
-
1956
- 1956-11-30 GB GB36775/56A patent/GB850015A/en not_active Expired
-
1957
- 1957-11-30 DE DEU4969A patent/DE1175804B/de active Pending
- 1957-11-30 DE DEU10271A patent/DE1223466B/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
- 1957-11-30 CH CH360137D patent/CH360137A/de unknown
-
1965
- 1965-03-26 NL NL6503923A patent/NL6503923A/xx unknown
Patent Citations (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 |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE4218023A1 (de) * | 1992-06-01 | 1993-12-02 | Siemens Ag | Brennstab eines Kernreaktors |
Also Published As
Publication number | Publication date |
---|---|
FR1187405A (fr) | 1959-09-10 |
BE562864A (enrdf_load_stackoverflow) | |
CH360137A (de) | 1962-02-15 |
NL6503923A (enrdf_load_stackoverflow) | 1965-05-25 |
GB850015A (en) | 1960-09-28 |
DE1223466B (de) | 1966-08-25 |
FR1187404A (fr) | 1959-09-10 |
NL128573C (enrdf_load_stackoverflow) | |
NL222873A (enrdf_load_stackoverflow) |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
DE1175804B (de) | Brennstoffelement fuer gasgekuehlte Kernreaktoren | |
DE2247685C3 (de) | Brennstoffelement | |
DE1206533B (de) | Kernreaktor-Brennstoffelement und Verfahren zu seiner Herstellung | |
DE3019175C2 (de) | Brennstoffkassette | |
DE3874180T2 (de) | Regelstab. | |
DE3619930C2 (enrdf_load_stackoverflow) | ||
DE19546597A1 (de) | Steuer-Absorberbündel für einen Kernreaktor | |
DE1214335B (de) | Stopfen fuer die Durchlaesse eines Kernreaktors | |
DE2808907C2 (enrdf_load_stackoverflow) | ||
DE1096511B (de) | Trag- bzw. Abstuetzvorrichtung fuer eine Brennstoffelementensaeule eines Kernreaktors | |
DE1489842A1 (de) | Rohrfoermiger Brennstoffstab fuer Kernreaktoren | |
DE1086355B (de) | Atomkernreaktor mit auf einem Traggitter innerhalb eines Druckgefaesses angeordneten Kernaufbau | |
DE1180857B (de) | Brennstoffelement fuer gasgekuehlte Kernreaktoren | |
DE1514081B2 (de) | Atomkernreaktor mit brenn und oder brutstoff in kugel foermigen gestalt | |
DE1220044B (de) | Vorrichtung zum Befestigen von Brennstoffelementbuendeln in Kernreaktoren | |
DE1179649B (de) | Brennstoffelement fuer Kernreaktoren | |
DE1233504B (de) | Keramisches Kernreaktor-Brennstoffelement | |
DE3226403A1 (de) | Brennelement, verfahren zu seiner herstellung und brennelementbehaelter | |
DE1127505B (de) | Gasgekuehlter, fluessigkeitsmoderierter Atomkernreaktor mit Umlenkkuehlung | |
DE1233502B (de) | Verfahren und Vorrichtung zum Befestigen von in einem Tragrohr uebereinandergestapelten Kernreaktor-Brennelementen | |
DE4018270A1 (de) | Hochtemperaturfeste steuerstab-anordnung | |
DE1614944A1 (de) | Reaktorbrennelemente in Form von Tabletten u.dgl. | |
DE1093495B (de) | Trag- und Stuetzvorrichtung fuer Kernreaktor-Brennstoffelemente | |
DE69600672T2 (de) | Kernbrennelement mit Brennstäben für gasgekühlten Reaktor | |
DE2608537A1 (de) | Brennstoffbehaelter fuer einen kernreaktor |