DE2429447A1 - Water cooled reactor fuel can with internal oxide coating - preventing metal water reaction if can bursts - Google Patents
Water cooled reactor fuel can with internal oxide coating - preventing metal water reaction if can burstsInfo
- Publication number
- DE2429447A1 DE2429447A1 DE2429447A DE2429447A DE2429447A1 DE 2429447 A1 DE2429447 A1 DE 2429447A1 DE 2429447 A DE2429447 A DE 2429447A DE 2429447 A DE2429447 A DE 2429447A DE 2429447 A1 DE2429447 A1 DE 2429447A1
- Authority
- DE
- Germany
- Prior art keywords
- water
- fuel
- oxide coating
- reaction
- bursts
- 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.)
- Withdrawn
Links
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
- G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
-
- 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)
- Other Surface Treatments For Metallic Materials (AREA)
Abstract
Description
Eernreaktorbrennstab Die vorliegende Erfindung betrifft einen Eernreaktorbrennstab für wassergekühlte Kernreaktoren, der aus einer Füllung aus Xernbrennstoff und einer Umhüllung aus einer Zirkon- oder Nioblegierung besteht. Aus einer Vielzahl solcher Brennstäbe setzt sich ein Kernreaktorbrennelement und der Reaktorkern aus einer Vielzahl solcher Brennelemente zusammen. Ein Brennxstab stellt somit die kleinste wärmeerzeugende Einheit in einem Reaktorkern dar.Iron reactor fuel rod The present invention relates to a nuclear reactor fuel rod for water-cooled nuclear reactors, which consists of a filling of Xernfuel and a Sheath consists of a zirconium or niobium alloy. From a multitude of such Fuel rods are made up of a nuclear reactor fuel assembly and the reactor core is made up of one Large number of such fuel assemblies together. A fuel rod is therefore the smallest heat-generating unit in a reactor core.
Diese Einheit hat aber auch den Zweck, den Kernbrennstoff sicher einzuschließen und die während des Abbrandes entstehenden Spaltprodukte zusammenzuhalten und an einem Austreten in das guhlmittel bzw. die Umgebung zu verhindern. Diese Aufgabenstellung wird während des normalen Reaktorbetriebes recht zufriedenstellend erfüllt. Sollte jedoch ein plötzlicher Kühlmittelverlust, z.B. durch Bruch einer Kühlmittelleitung auftreten, so kommt es sehr leicht zu Überhitzungen an den Brennstäben, wobei Temperaturen von 9000C und mehr erreicht werden können. Dies bedeutet aber,daß die Kernbrennstofffüllung noch auf wesentlich höhere Temperaturen wegen der nicht ausreichenden Kühlung kommt und sehr leicht Hüllrohrschäden auftreten können. Damit verbunden ist aber ein Eindringen des Kühlmittels in den Innenraum des betreffenden Brennstabes.However, this unit also has the purpose of safely enclosing the nuclear fuel and to hold together the fission products formed during the burn-up and to to prevent leakage into the coolant or the environment. This task is met quite satisfactorily during normal reactor operation. Should however, a sudden loss of coolant, e.g. due to a break in a coolant line occur, it is very easy to overheat the fuel rods, with temperatures of 9000C and more can be achieved. But this means that the nuclear fuel filling still comes to significantly higher temperatures because of the insufficient cooling and duct damage can occur very easily. But associated with this is an intrusion of the coolant in the interior of the fuel rod concerned.
Die verwendeten Legierungen für Hüllrohre auf Zirkon- oder Niobbasis haben aber die unangenehme Eigenschaft, daß sie bei Temperaturen über 9000C mit Wasser chemisch sehr stark reagieren, wobei aufgrund der freiwerdenden Wärme sehr rasch ein Schmelzen dieser Materialien und damit eine völlige Zerstörung eintritt.The alloys used for cladding tubes based on zirconium or niobium but have the unpleasant property that they with temperatures above 9000C with Water reacts very strongly chemically, whereby due to the heat released very strongly rapid melting of these materials and thus complete destruction occurs.
Das in der Kernreaktortechnik außerordentlich hohe Sicherheitsbedürfnis verlangt auch derartige Folgeerscheinungen von Reaktorunfällen mit Sicherheit auszuschließen. Eine Lösung dieses Problems besteht erfindungsgemäß darin, daß neben der Außenfläche auch besonders die Innenfläche des Hüllrohres zur Verhinderung einer Reaktion zwischen dem Hüllrohrmaterial und dem im Schadensfall in das Brennstabinnere eingedrungenen Wasser mit einer wenigstens 2 /um starken Oxidschicht versehen ist.The extraordinarily high security requirement in nuclear reactor technology also demands that such consequences of reactor accidents can be ruled out with certainty. A solution to this problem is, according to the invention, that in addition to the outer surface also especially the inner surface of the cladding tube to prevent a reaction between the cladding tube material and that which penetrated the inside of the fuel rod in the event of damage Water is provided with an at least 2 / µm thick oxide layer.
Auf der Außenseite der Hüllrohre bildet sich bereits während des normalen Reaktorbetriebes eine ausreichend dicke Oxidschicht. Sicherheitshalber sollte diese bereits während der Anfahrphase des Kernreaktors vorhanden sein, wie sie aus anderen Gründen bereits bei einzelnen früheren Brennstabkonstruktionen vorgesehen war. Die Innenwandung der Hüllrohre jedoch blieb bisher während des ganzen Reaktorbetriebes auf jeden Fall metallisch blank, so daß bei einem plötzlichen Wassereinbruch durch ein Leck und den bereits genannten hohen Temperaturen über 9000C die Gefahr der beschriebenen Reaktion besteht. Ausgedehnte Versuche haben erwiesen, daß bei einer Voroxidation der flüllrohrinnenwandung in einer Dicke von etwa 2 /um die Wasserreaktion des Hüllrohres sowie die damit verbundene weitere Temperaturerhöhung außerordentlich stark verlangsamt wird. Dabei findet eine weitere Selbstoxidation statt, die in zunehmendem Maße eine weitere Metall-Wasserreaktion unterbindet. Dieser Punkt ist bei einer Temperatur von ca. 100000 nach Ausbildung einer Schichtdicke der Oxidhaut von etwa 100 /um erreicht.On the outside of the cladding tubes already forms during normal A sufficiently thick oxide layer during reactor operation. To be on the safe side, this should already be present during the start-up phase of the nuclear reactor, as from others Reasons was already provided for in individual earlier fuel rod designs. the The inner wall of the cladding tubes, however, has remained in place during the entire operation of the reactor in any case bare metal, so that in the event of a sudden water ingress through a leak and the already mentioned high temperatures above 9000C the risk of described reaction exists. Extensive tests have shown that in one Preoxidation of the inner wall of the filler tube in a thickness of about 2 / around the water reaction of the cladding tube and the associated further increase in temperature are extraordinary is greatly slowed down. Another self-oxidation takes place, which in increasingly prevents another metal-water reaction. This point is at a temperature of approx. 100,000 after a layer thickness of the oxide skin has formed of about 100 / µm.
Die aufzubringende Oxidschicht kann in an sich bekannter Weise entweder durch galvanische Methoden oder auch durch Wasserdampfbehandlung, Oxidation mit Luft oder Sauerstoff, Aufdampftechnik, Gaszersetzung usw. erfolgen.The oxide layer to be applied can either be in a manner known per se by galvanic methods or by steam treatment, oxidation with Air or oxygen, vapor deposition, gas decomposition, etc.
Die Endkappen der Hüllrohre sind der Gefahr derartiger Reaktionen praktisch nicht ausgesetzt, da sie in wesentlich kühleren Zonen und in einiger Entfernung vom Kernreaktorbrennstoff liegen. Dies gilt auch für die Verbindungszonen zwischen Hüllrohr und Endkappen, die von einer derartigen Oxidationsschicht freigehalten werden müssen, da sonst keine einwandfreie Schweißverbindung erzielt werden kann.The end caps of the ducts are at risk of such reactions practically not exposed as they are in much cooler areas and at some distance from nuclear reactor fuel. This also applies to the connection zones between Cladding tube and end caps, which are kept free from such an oxidation layer otherwise a perfect welded joint cannot be achieved.
Es ist jedoch vorteilhaft, insbesondere auch jene Strukturteile eines Brennelementes, die an den Hüllrohren anliegen, wie z.B.However, it is advantageous, in particular, to include those structural parts of a Fuel assembly that rest on the cladding tubes, such as e.g.
Abstandshalter mit Oxidüberzügen zu versehen, damit auch von dieser Seite zusätzliche Temperaturzunahmen unterbunden werden.To provide spacers with oxide coatings, thus also from this Side additional temperature increases are prevented.
1 Patentanspruch1 claim
Claims (1)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2429447A DE2429447A1 (en) | 1974-06-19 | 1974-06-19 | Water cooled reactor fuel can with internal oxide coating - preventing metal water reaction if can bursts |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2429447A DE2429447A1 (en) | 1974-06-19 | 1974-06-19 | Water cooled reactor fuel can with internal oxide coating - preventing metal water reaction if can bursts |
Publications (1)
Publication Number | Publication Date |
---|---|
DE2429447A1 true DE2429447A1 (en) | 1976-01-08 |
Family
ID=5918421
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE2429447A Withdrawn DE2429447A1 (en) | 1974-06-19 | 1974-06-19 | Water cooled reactor fuel can with internal oxide coating - preventing metal water reaction if can bursts |
Country Status (1)
Country | Link |
---|---|
DE (1) | DE2429447A1 (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2833396A1 (en) * | 1977-08-01 | 1979-02-15 | Gen Electric | NUCLEAR FUEL ELEMENT WITH A COMPOSITE COVER |
FR2400750A1 (en) * | 1977-08-19 | 1979-03-16 | Kraftwerk Union Ag | PROCESS FOR PROTECTING THE CLADDING TUBES OF THE COMBUSTIBLE BARS OF A NUCLEAR REACTOR |
EP0116888A1 (en) * | 1983-02-18 | 1984-08-29 | Kraftwerk Union Aktiengesellschaft | Process for treating surfaces of finished parts, especially of tubes and range spacers, made from zirconium alloys for nuclear reactor fuel elements |
US6512806B2 (en) | 1996-02-23 | 2003-01-28 | Westinghouse Atom Ab | Component designed for use in a light water reactor, and a method for the manufacture of such a component |
-
1974
- 1974-06-19 DE DE2429447A patent/DE2429447A1/en not_active Withdrawn
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2833396A1 (en) * | 1977-08-01 | 1979-02-15 | Gen Electric | NUCLEAR FUEL ELEMENT WITH A COMPOSITE COVER |
FR2400750A1 (en) * | 1977-08-19 | 1979-03-16 | Kraftwerk Union Ag | PROCESS FOR PROTECTING THE CLADDING TUBES OF THE COMBUSTIBLE BARS OF A NUCLEAR REACTOR |
EP0116888A1 (en) * | 1983-02-18 | 1984-08-29 | Kraftwerk Union Aktiengesellschaft | Process for treating surfaces of finished parts, especially of tubes and range spacers, made from zirconium alloys for nuclear reactor fuel elements |
US6512806B2 (en) | 1996-02-23 | 2003-01-28 | Westinghouse Atom Ab | Component designed for use in a light water reactor, and a method for the manufacture of such a component |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
OB | Request for examination as to novelty | ||
OC | Search report available | ||
OD | Request for examination | ||
8130 | Withdrawal |