DE1068821B - - Google Patents
Info
- Publication number
- DE1068821B DE1068821B DENDAT1068821D DE1068821DA DE1068821B DE 1068821 B DE1068821 B DE 1068821B DE NDAT1068821 D DENDAT1068821 D DE NDAT1068821D DE 1068821D A DE1068821D A DE 1068821DA DE 1068821 B DE1068821 B DE 1068821B
- Authority
- DE
- Germany
- Prior art keywords
- fissile material
- pieces
- fuel element
- fissile
- graphite
- 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
-
- 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
- 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
-
- 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)
- Manufacturing & Machinery (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Manufacture Of Alloys Or Alloy Compounds (AREA)
Description
Die Erfindung bezieht sich auf ein Brennstoffelement für einen Kernreaktor mit mindestens einem in den SpaltstofEstab eingebetteten und von einem Wärmeträger durchfiossenen Kühlrohr, welches erzeugte Wärme aus dem Spaltstoff entnimmt.The invention relates to a fuel element for a nuclear reactor with at least one Embedded in the fissile material rod and traversed by a heat transfer medium, which generated Removes heat from the fissile material.
In Verbindung mit einer anderen Gattung von Brennstoffelementen ist es an sich bekannt, einen Spaltstoffstab in mehrere Spaltstoffstücke zu unterteilen, um durch eine solche Unterteilung Formänderungen an den Uranstäben während des Reaktorbetriebes zu unterbinden.In connection with another type of fuel element, it is known per se to have a Subdivide the fissile material rod into several pieces of fissile material in order to change the shape through such a subdivision to prevent on the uranium rods during reactor operation.
Die Erfindung ist dadurch gekennzeichnet, daß der Spaltstoffstab in an sich bekannter Weise in mehrere Spaltstoffstücke unterteilt ist und daß die Spaltstoffstücke mit axialem Abstand voneinander auf das mindeste eine in den Spaltstoffstab eingebettete Kühlrohr aufgereiht sind.The invention is characterized in that the fission material rod in a known manner in several Fissile pieces is divided and that the pieces of fissile material with an axial distance from each other to the minimum a cooling pipe embedded in the fissile material rod are lined up.
Hierbei wird insbesondere erzielt, daß die Spaltstoffstücke in dem in den Spaltstoffstab eingebetteten Kühlrohr ihr gemeinsames festes Rückgrat finden, welches sie unter anderem auch in hinreichendem axialem Abstand voneinander hält und daher verhütet, daß bei einer auftretenden Formänderung eines der Uranstücke auch die nächstliegenden Uranstücke mehr oder minder mit in Mitleidenschaft gezogen werden.What is achieved here in particular is that the fissile material pieces are embedded in the fissile material rod Cooling tube find their common solid backbone, which they also find in sufficient axial distance from each other and therefore prevents that when a change in shape occurs of the uranium pieces, the closest pieces of uranium were also more or less affected will.
Ferner wird hierdurch erzielt, daß Ablösungen in der Grenzschicht zwischen dem SpaltstofF und dem in ihn eingebetteten Kühlrohr, die sich im Laufe des Betriebes des Reaktors selbst dann ereignen können, wenn anfangs eine intermetallische Bindung in der Grenzschicht erzielt war, durch den Abstand der Spaltstoffstücke abgestoppt werden, wodurch verhindert wird, daß sie sich auf das nächste Spaltstoffstück fortpflanzen.This also ensures that delaminations in the boundary layer between the fissile material and the in it is embedded cooling tube, which can occur during the operation of the reactor itself, if an intermetallic bond was initially achieved in the boundary layer, by the distance between the Fissile material pieces are stopped, which prevents them from affecting the next piece of fissile material propagate.
Solche Ablösungen würden die Wärmeübertragung vom SpaltstofE auf das Kühlrohr erschweren, dadurch lokale Überhitzungen des Spaltstoffes und schließlich ein Schmelzen von Teilen des Spaltstoffes zur Folge haben.Such detachments would make the heat transfer from the fissile material to the cooling pipe more difficult local overheating of the fissile material and finally a melting of parts of the fissile material result to have.
Um dem Entstehen solcher Ablösungen noch mehr entgegenzuwirken, kann die das Kühlrohr umgebende Spaltstoffschicht mit Hilfe von Längsschlitzen und/oder quer gerichteten Schlitzen, z. B. auch schraubenförmigen, außerdem noch in kleinere Felder unterteilt sein, wobei diese Schlitze die Spaltstoffschicht entweder nur von außen anschlitzen und so· nur in den äußeren Teilen der Spaltstoffschicht die entstehenden Spannungen unterbrechen oder die Spaltstoffschicht bis auf die Grenzschicht zum Kühlrohr hinab durdhschlitzen können.In order to counteract the occurrence of such detachments even more, the one surrounding the cooling tube can Fissile material layer with the help of longitudinal slots and / or transversely directed slots, e.g. Belly helical, furthermore still be divided into smaller fields, whereby these slots the fissile material layer either only slit from the outside and thus · only in the outer parts of the layer of fissile material Interrupt tensions or the layer of fissile material down to the boundary layer to the cooling pipe be able to slit down through it.
Die Zusammenfassung der im Brennstoffelement enthaltenen Spaltstoffstäbe kann mittels eines Graphitrohres
geschehen, und die Zwischenräume zwischen Kernreaktor-Brennstoffelement
und Verfahren zu seiner HerstellungThe combination of the fuel rods contained in the fuel element can be done by means of a graphite tube, and the spaces between the nuclear reactor fuel element
and its method of manufacture
Anmelder:Applicant:
Gebrüder Sulzer Aktiengesellschaft,
Winterthur (Sdiweiz)Sulzer Brothers Aktiengesellschaft,
Winterthur (Southern Switzerland)
Vertreter: Dipl.-Ing. H. Marsch, Patentanwalt, Schwelm, Drosselstr. 31Representative: Dipl.-Ing. H. Marsch, patent attorney, Schwelm, Drosselstr. 31
Beanspruchte Priorität: j- Schweiz vom 12. September 1957Claimed priority: j- Switzerland of September 12, 1957
den einzelnen Spaltstoffstäben sowie zwischen diesen a5 und dem Graphitrohr können mit Kohlenstoff, z. B.
mit Graphit gefüllt sein. Hierdurch wird erzielt, daß etwa, wie vorstehend beschrieben, vom Kühlrohr abgelöste
Spaltstoffteile trotzdem, und zwar durch den Kohlenstoff und Graphit, in ihrer Lage am Kuhlrohr
festgehalten werden, so daß sie, falls sie schmelzen sollten, sich nicht vom Kühlrohr entfernen, sondern
der kühlen Oberfläche desselben wieder, zufließen und so erneut gekühlt werden und wieder erstarren.
Das durch das Graphitrohr zusammengefaßte Spalt-Stoffelement kann unter Zwischenschaltung einer
Wärmeisolierschicht außen durch einen gasdichten Mantel aus einem neutronendurchlässigen Metall geschützt
sein.the individual fissile material rods and between these a5 and the graphite tube can with carbon, z. B. filled with graphite. This ensures that, for example, as described above, detached pieces of fissile material from the cooling tube are still held in their position on the cooling tube by the carbon and graphite, so that if they should melt, they do not move away from the cooling tube, but rather the cool surface of the same again, flow in and are thus cooled again and solidify again.
The summarized by the graphite tube fission fuel element can interposition be protected by a gas-tight sheath of a neutron permeable metal of a heat insulating layer outside.
Die Erfindung bezieht sich ferner auf ein Verfahren zum Herstellen eines Spaltstoffstabes für das Spaltstoffelement, welches dadurch gekennzeichnet ist, daß man die vorbereiteten, den einzubettenden Kühlrohren entsprechend gelochten Spaltstoffstücke, unter Zwischenlegen von Abstandhalten!, auf das mindestens eine einzubettende Kühlrohr aufreiht, den in dieser Weise vorläufig zusammengereihten Spaltstoffstab in eine stehende, der Oberfläche der Spaltstoffstücke angepaßte Kokille stellt und ihn zusammen mit dieser in einen Vakuumbehälter bringt, in welchem die Spaltstoffstücke so weit erhitzt werden, daß sie schmelzend auf den jeweiligen Abstandhalter absinken, sich nach außen hin der Innenwand der Kokille anschmiegen und nach innen hin eine intermetallische Bindung mit der Oberfläche des Kühlrohres eingehen.The invention further relates to a method for producing a rod of fissile material for the fissile material element, which is characterized in that the prepared cooling tubes to be embedded appropriately perforated pieces of fissile material, with spacers between them! to the minimum a cooling pipe to be embedded lined up, the fissile material rod, which was temporarily lined up in this way, in a standing mold adapted to the surface of the fissile material pieces and put it together with this brings into a vacuum container in which the pieces of fissile material are heated so far that they melt Sink down onto the respective spacer and cling to the outside of the inner wall of the mold and inwardly enter into an intermetallic bond with the surface of the cooling tube.
309 648/327309 648/327
Claims (9)
Schweizerische Patentschrift Nr. 286 658;
französische Patentschrift Nr. 1 126 414;
britische Patentschrift Nr. 754 183;
USA.-Patentschrift Nr. 2 798 848;
»Atomics«, 8, Nr. 1, 1957, S. 5;
»Nucleonics«, 14, Nr. 12, 1956, S. 14;
»Genfer Berichte«, Bd. 3, 1955, S. 337.Considered publications:
Swiss Patent No. 286 658;
French Patent No. 1,126,414;
British Patent No. 754 183;
U.S. Patent No. 2,798,848;
"Atomics", 8, No. 1, 1957, p. 5;
"Nucleonics", 14, No. 12, 1956, p. 14;
"Geneva Reports", Vol. 3, 1955, p. 337.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CH838838X | 1957-09-12 |
Publications (1)
Publication Number | Publication Date |
---|---|
DE1068821B true DE1068821B (en) | 1959-11-12 |
Family
ID=4541005
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DENDAT1068821D Pending DE1068821B (en) | 1957-09-12 |
Country Status (5)
Country | Link |
---|---|
BE (1) | BE571126A (en) |
CH (1) | CH351347A (en) |
DE (1) | DE1068821B (en) |
FR (1) | FR1197317A (en) |
GB (1) | GB838838A (en) |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1177261B (en) * | 1960-03-05 | 1964-09-03 | Siemens Ag | Nuclear reactor fuel rod |
US3184392A (en) * | 1959-08-17 | 1965-05-18 | Atomic Energy Authority Uk | Fast nuclear reactor fuel elements |
DE1213064B (en) * | 1960-06-28 | 1966-03-24 | Atomenergikommissionen | Process for the manufacture of nuclear reactor fuel elements |
DE1215826B (en) * | 1960-07-25 | 1966-05-05 | Siemens Planiawerke Ag | Method of making a nuclear reactor fuel element |
DE1217514B (en) * | 1959-06-03 | 1966-05-26 | Philips Nv | Fuel element for nuclear reactors |
DE1233505B (en) * | 1961-03-09 | 1967-02-02 | Anglo Belge Vulcain Sa Soc | Reactor core component |
DE1248176B (en) * | 1961-03-21 | 1967-08-24 | Sigri Elektrographit Gmbh | Nuclear reactor fuel element for high temperatures |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3178354A (en) * | 1961-07-25 | 1965-04-13 | Jackson & Moreland Inc | Steam cooled nuclear reactor system with improved fuel element assembly |
BE624769A (en) * | 1961-11-15 | 1900-01-01 | ||
NL288110A (en) * | 1962-02-08 | 1900-01-01 | ||
NL281496A (en) * | 1962-06-13 | 1900-01-01 | ||
US3274070A (en) * | 1963-05-31 | 1966-09-20 | Gen Dynamics Corp | Fuel element with improved purge gas arrangement |
GB8312693D0 (en) * | 1983-05-09 | 1983-06-15 | Darchem Ltd | Composite metal articles |
GB2282478B (en) * | 1993-10-01 | 1997-08-13 | Us Energy | Method of fabricating 99Mo production targets using low enriched uranium |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH286658A (en) * | 1950-11-09 | 1952-10-31 | Sulzer Ag | Process for harnessing atomic energy and nuclear reactor for carrying out the process. |
GB754183A (en) * | 1954-05-14 | 1956-08-01 | Asea Ab | Improvements in nuclear-chain reactors |
FR1126414A (en) * | 1955-02-16 | 1956-11-22 | Thomson Houston Comp Francaise | Further training in nuclear reactors |
US2798848A (en) * | 1951-07-13 | 1957-07-09 | Kenneth H Kingdon | Neutronic reactor fuel element |
-
0
- DE DENDAT1068821D patent/DE1068821B/de active Pending
- BE BE571126D patent/BE571126A/xx unknown
-
1957
- 1957-09-12 CH CH351347D patent/CH351347A/en unknown
-
1958
- 1958-06-18 FR FR1197317D patent/FR1197317A/en not_active Expired
- 1958-09-12 GB GB29325/58A patent/GB838838A/en not_active Expired
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH286658A (en) * | 1950-11-09 | 1952-10-31 | Sulzer Ag | Process for harnessing atomic energy and nuclear reactor for carrying out the process. |
US2798848A (en) * | 1951-07-13 | 1957-07-09 | Kenneth H Kingdon | Neutronic reactor fuel element |
GB754183A (en) * | 1954-05-14 | 1956-08-01 | Asea Ab | Improvements in nuclear-chain reactors |
FR1126414A (en) * | 1955-02-16 | 1956-11-22 | Thomson Houston Comp Francaise | Further training in nuclear reactors |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1217514B (en) * | 1959-06-03 | 1966-05-26 | Philips Nv | Fuel element for nuclear reactors |
US3184392A (en) * | 1959-08-17 | 1965-05-18 | Atomic Energy Authority Uk | Fast nuclear reactor fuel elements |
DE1177261B (en) * | 1960-03-05 | 1964-09-03 | Siemens Ag | Nuclear reactor fuel rod |
DE1213064B (en) * | 1960-06-28 | 1966-03-24 | Atomenergikommissionen | Process for the manufacture of nuclear reactor fuel elements |
DE1215826B (en) * | 1960-07-25 | 1966-05-05 | Siemens Planiawerke Ag | Method of making a nuclear reactor fuel element |
DE1233505B (en) * | 1961-03-09 | 1967-02-02 | Anglo Belge Vulcain Sa Soc | Reactor core component |
DE1248176B (en) * | 1961-03-21 | 1967-08-24 | Sigri Elektrographit Gmbh | Nuclear reactor fuel element for high temperatures |
Also Published As
Publication number | Publication date |
---|---|
GB838838A (en) | 1960-06-22 |
FR1197317A (en) | 1959-11-30 |
BE571126A (en) | |
CH351347A (en) | 1961-01-15 |
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