DE102011004821B3 - Method for stabilizing blocked fuel assembly when loading/unloading core of nuclear reactor, involves compensating difference between buoyancy and gravitational forces acting on fuel assembly and moving object by buoyancy element - Google Patents
Method for stabilizing blocked fuel assembly when loading/unloading core of nuclear reactor, involves compensating difference between buoyancy and gravitational forces acting on fuel assembly and moving object by buoyancy element Download PDFInfo
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- DE102011004821B3 DE102011004821B3 DE102011004821A DE102011004821A DE102011004821B3 DE 102011004821 B3 DE102011004821 B3 DE 102011004821B3 DE 102011004821 A DE102011004821 A DE 102011004821A DE 102011004821 A DE102011004821 A DE 102011004821A DE 102011004821 B3 DE102011004821 B3 DE 102011004821B3
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- fuel assembly
- buoyancy
- fuel
- loading
- stabilizing
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- 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
- G21C19/26—Arrangements for removing jammed or damaged fuel elements or control elements; Arrangements for moving broken parts thereof
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B66—HOISTING; LIFTING; HAULING
- B66C—CRANES; LOAD-ENGAGING ELEMENTS OR DEVICES FOR CRANES, CAPSTANS, WINCHES, OR TACKLES
- B66C1/00—Load-engaging elements or devices attached to lifting or lowering gear of cranes or adapted for connection therewith for transmitting lifting forces to articles or groups of articles
- B66C1/10—Load-engaging elements or devices attached to lifting or lowering gear of cranes or adapted for connection therewith for transmitting lifting forces to articles or groups of articles by mechanical means
- B66C1/62—Load-engaging elements or devices attached to lifting or lowering gear of cranes or adapted for connection therewith for transmitting lifting forces to articles or groups of articles by mechanical means comprising article-engaging members of a shape complementary to that of the articles to be handled
- B66C1/66—Load-engaging elements or devices attached to lifting or lowering gear of cranes or adapted for connection therewith for transmitting lifting forces to articles or groups of articles by mechanical means comprising article-engaging members of a shape complementary to that of the articles to be handled for engaging holes, recesses, or abutments on articles specially provided for facilitating handling thereof
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- 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
- G21C19/02—Details of handling arrangements
- G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
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- 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
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
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- 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
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
Die Erfindung bezieht sich auf ein Verfahren und eine Vorrichtung zum Stabilisieren eines beim Be- oder Entladen eines Kerns eines Kernreaktors in einer Zwischenposition blockierten Brennelementes.The invention relates to a method and an apparatus for stabilizing a fuel element blocked in loading or unloading a core of a nuclear reactor in an intermediate position.
Aus zahlreichen Inspektionsresultaten ist es bekannt, dass sich insbesondere die Brennelemente eines Druckwasserkernreaktors im Laufe ihrer Einsatzdauer in Abhängigkeit von ihrer Position im Kern verbiegen. Ursachen hierfür können beispielsweise Anisotropien in der thermischen Längenausdehnung, ein durch radioaktive Strahlung induziertes Längenwachstum der Brennstabhüllrohre oder der Steuerstabführungsrohre oder Strömungskräfte sein, die durch quer zur Längsachse der Brennelemente gerichtete Ausgleichsströmungen erzeugt werden. Diese Durchbiegungen können zu Problemen beim Brennelementwechsel führen.From numerous inspection results it is known that, in particular, the fuel elements of a pressurized-water nuclear reactor bend over their service life, depending on their position in the core. Causes for this can be, for example, anisotropies in the thermal linear expansion, a radiation-induced lengthwise growth of the fuel rod cladding tubes or the control rod guide tubes or flow forces that are generated by transversely directed to the longitudinal axis of the fuel flow compensating flows. These deflections can lead to problems during fuel assembly change.
So kann es im ungünstigsten Fall vorkommen, dass sich ein Brennelement beim Be- oder Entladevorgang mit einem in einer unmittelbar benachbarten Position befindlichen Brennelement verhakt, so dass der Ladevorgang abgebrochen werden muss, um eine Beschädigung des Brennelementes und eine damit möglicherweise verbundene Freisetzung radioaktiver Substanzen zu verhindern. Das in einer solchen Zwischenposition blockierte, und über dem Kern vorstehende Brennelement muss dann mit geeigneten Werkzeugen auf aufwendige Weise befreit werden, um einen weiteren Betrieb der Kraftwerksanlage zu ermöglichen.Thus, it may happen in the worst case that a fuel element hooked during loading or unloading with a located in an immediately adjacent position fuel assembly, so that the charging must be canceled to damage the fuel assembly and thus possibly associated release of radioactive substances prevent. The blocked in such an intermediate position, and above the core projecting fuel element must then be freed with suitable tools in a complex manner to allow further operation of the power plant.
Um ein solches blockiertes Brennelement zu befreien, ist es im Stand der Technik bekannt, ein oder mehrere in einer Nachbarposition befindliche Elemente, bei denen es sich um Brennelemente oder um sogenannte Brennelement-Dummys (im nachfolgenden Text wird vereinfacht nur der Begriff „Brennelement” verwendet) handeln kann, mit Hilfe eines sogenannten Brennelement-Einfachgreifers zuziehen, um auf diese Weise den vorhandenen Freiraum in der Umgebung des blockierten Brennelementes zu vergrößern. Problematisch hierbei ist, dass sich solche Nachbarpositionen zwangsläufig unterhalb der durch das blockierte Brennelement ebenfalls blockierten Brennelement-Wechselmaschine befindet, so dass diese nicht mit einem in der Kraftwerksanlage vorhandenen Einfachgreifer erreichbar sind, da dieser mit dem Gebäudekran exakt vertikal über dem jeweils zu ziehenden Nachbarelement positioniert werden muss. Um ein Ziehen benachbarter Brennelemente zu ermöglichen, wurde deshalb unterhalb der Brennelement-Wechselmaschine eine Gerüstbühne eingezogen, von der aus das oder die Nachbarelemente gezogen wurden. Eine solche Vorgehensweise erfordert jedoch einen hohen Aufwand und in der für den Aufbau erforderlichen Zeit konnte der weitere Belade- und Entladevorgang nicht fortgesetzt werden.In order to free such a blocked fuel element, it is known in the art, one or more located in a neighboring position elements, which are fuel or so-called fuel element dummies (in the following text is simplified, only the term "fuel" used ) can draw, with the help of a so-called fuel element single gripper to increase in this way the existing space in the vicinity of the blocked fuel assembly. The problem here is that such neighboring positions is inevitably below the blocked by the fuel assembly also blocked fuel alternator, so that they are not available with a present in the power plant single gripper, as this positioned with the building crane exactly vertically above each to be pulled adjacent element must become. In order to allow pulling of adjacent fuel elements, therefore, a scaffolding platform was pulled in from below the fuel assembly changing machine, from which the neighboring element or elements were pulled. However, such a procedure requires a lot of effort and in the time required for the construction of the further loading and unloading could not be continued.
Beim Be- oder Entladen eines Kerns ist es außerdem aus der
Der Erfindung liegt daher die Aufgabe zugrunde, ein Verfahren und eine Vorrichtung zum Stabilisieren eines beim Be- oder Entladen eines Kerns eines Kernreaktors in einer Zwischenposition blockierten Brennelementes anzugeben, mit dem es möglich ist, mit geringem baulichen Aufwand unterhalb der Brennelement-Wechselmaschine befindliche benachbarte Elemente zu ziehen.The invention is therefore based on the object of specifying a method and a device for stabilizing a blocked during loading or unloading of a core of a nuclear reactor in an intermediate position fuel element, with which it is possible, with little structural effort below the fuel assembly changing machine located adjacent elements to draw.
Hinsichtlich des Verfahrens wird die genannte Aufgabe gemäß der Erfindung gelöst mit einem Verfahren mit den Merkmalen des Patentanspruches 1. Gemäß diesen Merkmalen umfasst das Verfahren zum Stabilisieren eines beim Be- oder Entladen eines Kerns eines Kernreaktors in einer Zwischenposition blockierten Brennelementes folgende Verfahrensschritte:
- a) Im Bereich eines Kopfteils des mit einem Greifer einer Brennelement-Wechselmaschine in dieser Zwischenposition gehaltenen Brennelementes wird ein mit zumindest einem Antriebsaggregat und mit zumindest einem zumindest teilweise gefluteten Auftriebskörper versehenes selbstfahrendes Tauchfahrzeug positioniert,
- b) am Tauchfahrzeug angeordnete Haltemittel werden mit dem Kopfteil des Brennelementes in Eingriff gebracht,
- c) anschließend wird der zumindest eine Auftriebskörper soweit entleert, dass durch die auf das Tauchfahrzeug wirkende Differenz aus Auftriebskraft und Gewichtskraft die auf das Brennelement wirkende Differenz aus Auftriebskraft und Gewichtskraft zumindest kompensiert wird,
- d) der Greifer der Brennelement-Wechselmaschine der wird vom Brennelement gelöst und aus dem Tauchfahrzeug gezogen, so dass er seitlich vom Brennelement weggefahren werden kann.
- a) in the region of a head portion of the held with a gripper of a fuel assembly changing machine in this intermediate position fuel assembly is provided with at least one drive unit and at least one at least partially flooded buoyancy self-propelled submersible,
- b) retaining means arranged on the submersible vehicle are brought into engagement with the head part of the fuel assembly,
- c) the at least one buoyant body is subsequently emptied to such an extent that the difference between buoyancy force and weight force acting on the fuel element is at least compensated by the difference between buoyancy force and weight force acting on the submersible vehicle,
- d) the gripper of the fuel assembly changing machine is released from the fuel assembly and pulled out of the submersible vehicle, so that it can be moved away from the side of the fuel assembly.
Durch diese Vorgehensweise kann die Brennelement-Wechselmaschine in eine Position über ein benachbartes Brennelement verfahren werden, um dieses zu ziehen und auf diese Weise den in der Reihe oder in der Spalte, in der sich das blockierte Brennelement befindet, verfügbaren Freiraum zu vergrößern.By doing so, the fuel assembly machine can be moved to a position over an adjacent fuel assembly to pull it and thus increase the clearance available in the row or in the column where the jammed fuel assembly is located.
Hinsichtlich der Vorrichtung wird die Aufgabe gemäß der Erfindung gelöst mit einer Vorrichtung mit den Merkmalen des Patentanspruches 2, die sinngemäß den in Patentanspruch 1 genannten Merkmalen entsprechen.With regard to the device, the object is achieved according to the invention with a device having the features of
Weitere vorteilhafte Ausgestaltungen der Vorrichtung sind in den auf Patentanspruch 2 zurückbezogenen Unteransprüchen angegeben.Further advantageous embodiments of the device are specified in the dependent on
Zur weiteren Erläuterung der Erfindung wird auf das in den Figuren dargestellte Ausführungsbeispiel verwiesen. Es zeigen:For further explanation of the invention reference is made to the embodiment shown in the figures. Show it:
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DE102011004821A DE102011004821B3 (en) | 2011-02-28 | 2011-02-28 | Method for stabilizing blocked fuel assembly when loading/unloading core of nuclear reactor, involves compensating difference between buoyancy and gravitational forces acting on fuel assembly and moving object by buoyancy element |
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DE102011004821A DE102011004821B3 (en) | 2011-02-28 | 2011-02-28 | Method for stabilizing blocked fuel assembly when loading/unloading core of nuclear reactor, involves compensating difference between buoyancy and gravitational forces acting on fuel assembly and moving object by buoyancy element |
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Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109830315A (en) * | 2019-01-29 | 2019-05-31 | 哈尔滨工程大学 | A kind of expansion nuclear reactor |
CN114188056A (en) * | 2021-12-03 | 2022-03-15 | 中国原子能科学研究院 | Fuel pellet handling apparatus and method |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE19756244B4 (en) * | 1995-12-22 | 2006-05-24 | Framatome Anp Gmbh | Device for lifting, lowering and transporting at least one movable object arranged in a liquid-filled basin, and method for lifting, lowering and transporting such an article |
DE102007006969B4 (en) * | 2006-11-30 | 2008-10-02 | Areva Np Gmbh | Apparatus for assisting the loading or unloading of a core of a pressurized water reactor |
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- 2011-02-28 DE DE102011004821A patent/DE102011004821B3/en active Active
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE19756244B4 (en) * | 1995-12-22 | 2006-05-24 | Framatome Anp Gmbh | Device for lifting, lowering and transporting at least one movable object arranged in a liquid-filled basin, and method for lifting, lowering and transporting such an article |
DE102007006969B4 (en) * | 2006-11-30 | 2008-10-02 | Areva Np Gmbh | Apparatus for assisting the loading or unloading of a core of a pressurized water reactor |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109830315A (en) * | 2019-01-29 | 2019-05-31 | 哈尔滨工程大学 | A kind of expansion nuclear reactor |
CN114188056A (en) * | 2021-12-03 | 2022-03-15 | 中国原子能科学研究院 | Fuel pellet handling apparatus and method |
CN114188056B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Fuel pellet handling apparatus and method |
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