WO1994011881A1 - Arrangement for clamping a reactor shaft arranged in a reactor pressure vessel - Google Patents

Arrangement for clamping a reactor shaft arranged in a reactor pressure vessel Download PDF

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Publication number
WO1994011881A1
WO1994011881A1 PCT/DE1993/001004 DE9301004W WO9411881A1 WO 1994011881 A1 WO1994011881 A1 WO 1994011881A1 DE 9301004 W DE9301004 W DE 9301004W WO 9411881 A1 WO9411881 A1 WO 9411881A1
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WO
WIPO (PCT)
Prior art keywords
reactor
pressure vessel
clamping
shaft
arrangement according
Prior art date
Application number
PCT/DE1993/001004
Other languages
German (de)
French (fr)
Inventor
Ulrich Nestler
Original Assignee
Siemens Aktiengesellschaft
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Siemens Aktiengesellschaft filed Critical Siemens Aktiengesellschaft
Priority to UA95048346A priority Critical patent/UA27940C2/en
Priority to RU95110056/06A priority patent/RU2144705C1/en
Publication of WO1994011881A1 publication Critical patent/WO1994011881A1/en

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • 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

Definitions

  • the invention relates to an arrangement for bracing a reactor shaft arranged in a reactor pressure vessel against the cover of the reactor pressure vessel.
  • compensator tube segments In pressurized water reactors of the WER series, the core built-in supporting reactor shaft is braced against the cover of the reactor pressure vessel by so-called compensator tube segments.
  • These compensator tube segments have the function of compensating for the buoyancy forces which arise from the hydraulic pressure processes within the reactor pressure vessel and act on the reactor internals and the reactor shaft. This is intended to produce stable clamping conditions for the reactor shaft in order to prevent or reduce damage processes occurring during operation due to wear and to ensure safe operation of the nuclear plant.
  • the known compensator tube segments apply the clamping forces required for stabilization through bracing and elastic deformation.
  • the invention is based on the object of specifying an arrangement for clamping a reactor shaft arranged in a reactor pressure vessel, which ensures stable clamping conditions over a long period of time and in which replacement measures caused by wear and tear only result in a small amount of radioactively contaminated waste .
  • this object is achieved by an arrangement for clamping a reactor shaft arranged in a reactor pressure vessel, in which a plurality of resilient clamping elements connected in parallel is provided between an upper collar of the reactor shaft and the cover of the reactor pressure vessel, which elements are arranged in such a way that that only an elastic deformation of these clamping elements is possible within a predetermined working path.
  • a mechanical stop is preferably arranged on the upper collar of the reactor shaft.
  • At least one guide rail is arranged on the cover of the reactor pressure vessel or on the upper collar of the reactor shaft, onto which the clamping elements are pushed. This measure enables easy mounting and dismounting of the clamping elements.
  • FIG. 1 shows an arrangement according to the invention in a longitudinal section through part of a reactor pressure vessel in the region of the cover.
  • FIG. 2 also shows a part of the reactor pressure vessel in the region of its cover in a longitudinal section at a different angle.
  • Figures 3 and 4 show part of the support collar of the lid and part of the collar of the reactor shaft in a plan view from below and from above.
  • a support collar 4 arranged on the cover 2 and one 6 chucking elements 10 are provided on the wall of the reactor pressure vessel 1 supporting core shaft 6. These clamping elements 10 clamp the reactor shaft 6 against the cover 2, which is firmly screwed to the housing of the reactor pressure vessel 1.
  • the clamping elements 10 comprise a guide sleeve 12 which are pushed onto a dovetail-like guide rail 8 arranged on the support collar 4.
  • the guide sleeve 12 surrounds a pressure stamp 14 which, when the guide sleeve 12 is pushed onto the guide rail 8, is pressed outwards by plate spring assemblies 16, which are supported on the guide rail 8 by a pressure ring 18, so that it projects beyond the guide sleeve 12.
  • the pressure stamp 14 is provided with a collar 142 which is supported on an annular projection 121 of the guide sleeve 12 when the pressure stamp 14 is deflected to the maximum extent caused by the action of the plate spring packages 16.
  • the annular projection 121 thus forms a mechanical stop for the pressure stamp 14.
  • leaf spring segments or compression spring segments such as, for example, spiral springs, can also be provided in the clamping elements.
  • the figure shows the situation in the installed state, in which there is a gap s between the collar 142 and the annular projection 121, which corresponds to a pretensioning of the clamping element 10.
  • a guide pin 20 is arranged on the pressure stamp to accommodate the plate spring assemblies 16.
  • the pressure stamp 14 is provided with a convex end face 141 which is supported in a concave shape 91 of a base bar 9 arranged on the upper collar 7 of the reactor shaft 6. This convex or concave design of the surfaces facing one another ensures that the pressure stamp 14 is centered.
  • the maximum possible predetermined working path s of the reactor shaft 6 is shown in the figure.
  • This working path s results from mechanical stops which are not visible in the figure and limits the possible stroke of the reactor shaft 6 against the reactor cover 2.
  • the working path s is smaller than the spring travel possible by the construction of the guide sleeve 12, for example are limited by the distance between the guide pin 20 and the end face of the guide rail 8 or the distance of the lower end face of the guide sleeve 12 from the base bar 9.
  • the plate spring assemblies 16 are dimensioned in such a way that plastic deformation of the plate spring assemblies 16 and thus of the clamping element 10 can be ruled out within this maximum working path s which is still possible in the installed state.
  • a guide rail 8 arranged on the upper collar 7 of the reactor shaft 6 can also be provided.
  • clamping elements can also be provided which are encapsulated in segment-like guide strips which are releasably connected to the upper collar 7 of the reactor shaft 6 in the positions provided for the compensator tube segments.
  • the formation of the maximum possible travel s can be seen from the illustration in FIG. 2. There, the work path s is effected by a dome-shaped mechanical stop 30 screwed to the reactor shaft.
  • FIG. 3 it can be seen that a plurality of ring rails 8 are provided in segment-like fashion on the support collar 4, onto each of which a large number of clamping elements 10 are pushed.
  • These clamping elements 10 are independent of one another and detachably connected to the guide rail 8 fixed to the support collar 4, which are checked independently of one another and, if necessary, can be individually replaced without any problems.
  • a plurality of segment-shaped base strips 9 are also provided according to FIG. 4, which have spherical shapes 91 corresponding to the number of clamping elements 10 . are provided.
  • the mechanical stops 30 arranged between the individual base strips 9 can also be seen in the figure.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Basic Packing Technique (AREA)
  • Particle Accelerators (AREA)

Abstract

According to the invention, an arrangement for clamping a reactor shaft (6) arranged in a reactor pressure vessel (1) contains a plurality of parallel-connected spring-loaded clamping components (10) between an upper collar (7) of the reactor shaft (6) and the cover (2) of the reactor pressure vessel (1) arranged in such a way that only one elastic deformation of said clamping components (10) is possible within a predetermined working stroke(s). This ensures stable clamping conditions over long periods. The use of individually exchangeable clamping components (10) also reduces the quantity of radioactively contaminated waste when such an exchange proves necessary.

Description

Anordnung zum Einspannen eines in einem Reaktordruckbe¬ hälter angeordneten Reaktorschachtes.Arrangement for clamping a reactor shaft arranged in a reactor pressure vessel.
Die Erfindung bezieht sich auf eine Anordnung zum Ver¬ spannen eines in einem Reaktordruckbehälter angeordneten Reaktorschachtes gegen den Deckel des Reaktordruckbehäl¬ ters.The invention relates to an arrangement for bracing a reactor shaft arranged in a reactor pressure vessel against the cover of the reactor pressure vessel.
Bei Druckwasserreaktoren der Baureihe WWER ist der Kern¬ einbauten tragende Reaktorschacht gegen den Deckel des Reaktordruckbehälters durch sogenannte Kompensatorrohrseg¬ mente verspannt. Diese Kompensatorrohrsegmente haben die Funktion, die durch ther ohydraulische Vorgänge innerhalb des Reaktordruckbehälters entstehenden und auf die Reak¬ toreinbauten und den Reaktorschacht wirkenden Auftriebs¬ kräfte zu kompensieren. Dadurch sollen stabile Einspann¬ verhältnisse für den Reaktorschacht erzeugt werden, um während des Betriebs durch Verschleiß auftretenden Schä¬ digungsprozesse zu verhindern oder zu verringern und eine sichere Betriebsweise der nuklearen Anlage zu gewährlei¬ sten. Die bekannten Kompensatorrohrsegmente bringen dabei die zur Stabilisierung erforderlichen Einspannkrafte durch Verspannung und elastische Verformung auf.In pressurized water reactors of the WWER series, the core built-in supporting reactor shaft is braced against the cover of the reactor pressure vessel by so-called compensator tube segments. These compensator tube segments have the function of compensating for the buoyancy forces which arise from the hydraulic pressure processes within the reactor pressure vessel and act on the reactor internals and the reactor shaft. This is intended to produce stable clamping conditions for the reactor shaft in order to prevent or reduce damage processes occurring during operation due to wear and to ensure safe operation of the nuclear plant. The known compensator tube segments apply the clamping forces required for stabilization through bracing and elastic deformation.
In der Praxis hat sich jedoch herausgestellt, daß die bekannten Kompensatorrohrsegmente teilweise schon nach einem Betriebsjahr große plastische Deformationen auf¬ weisen. Dies hat zur Folge, daß bei Weiterverwendung die¬ ser plastisch deformierten Kompensatorrohrsegmente eine Schädigung der Reaktoreinbauten nicht auszuschließen ist. Außerdem ist die Nachprüfung der elastischen Eigenschaf- ten eines bereits plastisch verformten Kompensatorrohr- segmentes ohne weitere plastische Verformung und damit verbundene Verringerung seiner Restelastizität, also Zer¬ störung seiner federnden Eigenschaften, nicht möglich.In practice, however, it has been found that the known compensator tube segments show large plastic deformations even after one year of operation. This has the consequence that damage to the reactor internals cannot be ruled out if these plastically deformed compensator tube segments are used further. In addition, the verification of the elastic properties An already plastically deformed compensator tube segment is not possible without further plastic deformation and the associated reduction in its residual elasticity, that is to say destruction of its resilient properties.
Darüberhinaus fällt beim Austausch dieser Rohrsegmente eine große Menge stark radioaktiv kontaminierten Abfalles an.In addition, a large amount of highly radioactive contaminated waste is generated when these pipe segments are replaced.
Der Erfindung liegt nun die Aufgabe zugrunde, eine Anord¬ nung zum Einspannen eines in einem Reaktordruckbehälter angeordneten Reaktorschachtes anzugeben, die über längere Zeit stabile Einspannverhältnisse gewährleistet und bei der durch eventuellen Verschleiß bedingte Austauschma߬ nahmen nur zu einer geringen Menge radioaktiv kontami¬ nierten Abfalls führen.The invention is based on the object of specifying an arrangement for clamping a reactor shaft arranged in a reactor pressure vessel, which ensures stable clamping conditions over a long period of time and in which replacement measures caused by wear and tear only result in a small amount of radioactively contaminated waste .
Die genannte Aufgabe wird gemäß der Erfindung durch eine Anordnung zum Einspannen eines in einem Reaktordruckbe¬ hälters angeordneten Reaktorschachtes gelöst, bei der zwischen einem oberen Bund des Reaktorschachtes und dem Deckel des Reaktordruckbehälters eine Vielzahl parallel¬ geschalteter federnder Einspannelemente vorgesehen ist, die derart angeordnet sind, daß innerhalb eines vorge¬ gebenen Arbeitsweges nur eine elastische Verformung dieser Einspannelemente möglich ist.According to the invention, this object is achieved by an arrangement for clamping a reactor shaft arranged in a reactor pressure vessel, in which a plurality of resilient clamping elements connected in parallel is provided between an upper collar of the reactor shaft and the cover of the reactor pressure vessel, which elements are arranged in such a way that that only an elastic deformation of these clamping elements is possible within a predetermined working path.
Da somit eine plastische Verformung dieser Einspannele¬ mente ausgeschlossen ist, sind sichere stabilisierende Einspannverhältnisse während einer längeren Betriebsdauer gewährleistet. Da außerdem eine Vielzahl voneinander unab¬ hängiger federnder Einspannelemente vorgesehen ist, müssen im Rahmen einer Wartung nur die Einspannelemente ausge¬ tauscht werden, bei denen tatsächlich ein Verschleiß fest- gestellt worden ist. Dadurch ist die Menge des anfallenden radioaktiven Abfalls reduziert.Since a plastic deformation of these clamping elements is thus ruled out, secure stabilizing clamping conditions are guaranteed over a longer period of operation. Since, in addition, a large number of mutually independent resilient clamping elements is provided, only those clamping elements that actually wear out need to be replaced during maintenance. has been asked. This reduces the amount of radioactive waste generated.
Zur Begrenzung des Arbeitsweges ist vorzugsweise am oberen Bund des Reaktorschachtes ein mechanischer Anschlag ange¬ ordnet.To limit the working distance, a mechanical stop is preferably arranged on the upper collar of the reactor shaft.
In einer weiteren bevorzugten Ausführungsform der Erfin¬ dung ist am Deckel des Reaktordruckbehälters oder am oberen Bund des Reaktorschachtes wenigstens eine Führungs¬ schiene angeordnet, auf die die Einspannelemente aufge¬ schoben sind. Durch diese Maßnahme wird eine leichte Mon¬ tage und Demontage der Einspannelemente ermöglicht.In a further preferred embodiment of the invention, at least one guide rail is arranged on the cover of the reactor pressure vessel or on the upper collar of the reactor shaft, onto which the clamping elements are pushed. This measure enables easy mounting and dismounting of the clamping elements.
Weitere vorteilhafte Ausgestaltungen der Erfindung ergeben sich gemäß der Unteransprüche.Further advantageous embodiments of the invention result from the subclaims.
Zur weiteren Erläuterung der Erfindung wird auf das Aus¬ führungsbeispiel der Zeichnung verwiesen, in derenTo further explain the invention, reference is made to the exemplary embodiment of the drawing, in which:
Figur 1 eine Anordnung gemäß der Erfindung in einem Längs¬ schnitt durch einen Teil eines Reaktordruckbehälters im Bereich des Deckels veranschaulicht ist.FIG. 1 shows an arrangement according to the invention in a longitudinal section through part of a reactor pressure vessel in the region of the cover.
In Figur 2 ist in einem Längsschnitt unter einem anderen Winkel ebenfalls ein Teil des Reaktordruckbehälters im Bereich seines Deckels dargestellt.FIG. 2 also shows a part of the reactor pressure vessel in the region of its cover in a longitudinal section at a different angle.
Figuren 3 und 4 zeigen ein Teil des Stützbundes des Deckels bzw. einen Teil des Bundes des Reaktorschachtes in einer Draufsicht von unten bzw. von oben.Figures 3 and 4 show part of the support collar of the lid and part of the collar of the reactor shaft in a plan view from below and from above.
Gemäß Figur 1 ist bei einem Reaktordruckbehälter 1 zwi¬ schen einen am Deckel 2 angeordneten Stützbund 4 und einem sich an der Wand des Reaktordruckbehälters 1 abstützenden Kerπschachtes 6 Einspannelemente 10 vorgesehen. Diese Ein¬ spannelemente 10 verspannen den Reaktorschacht 6 gegen den fest mit dem Gehäuse des Reaktordruckbehälters 1 ver¬ schraubten Deckel 2.According to FIG. 1, in a reactor pressure vessel 1 there is a support collar 4 arranged on the cover 2 and one 6 chucking elements 10 are provided on the wall of the reactor pressure vessel 1 supporting core shaft 6. These clamping elements 10 clamp the reactor shaft 6 against the cover 2, which is firmly screwed to the housing of the reactor pressure vessel 1.
Die Einspannelemente 10 umfassen eine Führungshülse 12, die auf eine am Stützbund 4 angeordnete schwalbenschwanz¬ ähnliche Führungsschiene 8 aufgeschoben sind.The clamping elements 10 comprise a guide sleeve 12 which are pushed onto a dovetail-like guide rail 8 arranged on the support collar 4.
Die Führungshülse 12 umgibt einen Druckstempel 14, der bei auf die Führungsschiene 8 aufgeschobener Führungs¬ hülse 12 durch Tellerfederpakete 16, die sich über einen Druckring 18 an der Führungsschiene 8 abstützen nach außen gedrückt wird, so daß er über die Führungshülse 12 hinaus¬ ragt. Der Druckstempel 14 ist mit einem Bund 142 versehen, der sich bei maximaler, durch die Wirkung der Tellerfeder¬ pakete 16 verursachten Auslenkung des Druckstempels 14 an einem ringförmigen Vorsprung 121 der Führungshülse 12 ab¬ stützt. Der ringförmige Vorsprung 121 bildet somit einen mechanischen Anschlag für den Druckstempel 14.The guide sleeve 12 surrounds a pressure stamp 14 which, when the guide sleeve 12 is pushed onto the guide rail 8, is pressed outwards by plate spring assemblies 16, which are supported on the guide rail 8 by a pressure ring 18, so that it projects beyond the guide sleeve 12. The pressure stamp 14 is provided with a collar 142 which is supported on an annular projection 121 of the guide sleeve 12 when the pressure stamp 14 is deflected to the maximum extent caused by the action of the plate spring packages 16. The annular projection 121 thus forms a mechanical stop for the pressure stamp 14.
Anstelle von Tellerfedern oder Tellerfederpaketen 16 kön¬ nen in den Einspannelementen auch Blattfedersegmente oder Druckfedersegmente, wie beispielsweise Spiralfedern, vor¬ gesehen sein.Instead of plate springs or plate spring assemblies 16, leaf spring segments or compression spring segments, such as, for example, spiral springs, can also be provided in the clamping elements.
In der Figur ist die Situation im eingebauten Zustand dar¬ gestellt, in der sich zwischen dem Bund 142 und dem ring¬ förmigen Vorsprung 121 ein Spalt s, ergibt, der einer Vorspannung des Einspannelementes 10 entspricht.The figure shows the situation in the installed state, in which there is a gap s between the collar 142 and the annular projection 121, which corresponds to a pretensioning of the clamping element 10.
Zur Aufnahme der Tellerfederpakete 16 ist am Druckstempel ein Führungszapfen 20 angeordnet. Der Druckstempel 14 ist mit einer konvexen Stirnfläche 141 versehen, die sich in einer konkaven Ausformung 91 einer am oberen Bund 7 des Reaktorschachtes 6 angeordneten Basisleiste 9 abstützt. Durch diese konvexe bzw. konkave Gestaltung der einander zugewandten Oberflächen wird eine Zentrierung des Druckstempels 14 gewährleistet.A guide pin 20 is arranged on the pressure stamp to accommodate the plate spring assemblies 16. The pressure stamp 14 is provided with a convex end face 141 which is supported in a concave shape 91 of a base bar 9 arranged on the upper collar 7 of the reactor shaft 6. This convex or concave design of the surfaces facing one another ensures that the pressure stamp 14 is centered.
In der Figur ist der maximal mögliche vorgegebene Arbeits¬ weg s des Reaktorschachtes 6 eingezeichnet. Dieser Arbeitsweg s ergibt sich durch in der Figur nicht sicht¬ bare mechanische Anschläge und begrenzt den möglichen Hub des Reaktorschachtes 6 gegen den Reaktordeckel 2. Der Arbeitsweg s ist dabei kleiner als die durch den konstruk¬ tiven Aufbau der Führungshülse 12 möglichen Federwege, die beispielsweise durch den Abstand zwischen dem Führungs¬ zapfen 20 und der Stirnfläche der Führungsschiene 8 oder dem Abstand der unteren Stirnfläche der Führungshülse 12 von der Basisleiste 9 begrenzt sind. Die Tellerfeder¬ pakete 16 sind derart dimensioniert, daß innerhalb dieses im eingebauten Zustand noch möglichen maximalen Arbeits¬ weges s eine plastische Verformung der Tellerfederpakete 16 und somit des Einspannelements 10 ausgeschlossen werden kann.The maximum possible predetermined working path s of the reactor shaft 6 is shown in the figure. This working path s results from mechanical stops which are not visible in the figure and limits the possible stroke of the reactor shaft 6 against the reactor cover 2. The working path s is smaller than the spring travel possible by the construction of the guide sleeve 12, for example are limited by the distance between the guide pin 20 and the end face of the guide rail 8 or the distance of the lower end face of the guide sleeve 12 from the base bar 9. The plate spring assemblies 16 are dimensioned in such a way that plastic deformation of the plate spring assemblies 16 and thus of the clamping element 10 can be ruled out within this maximum working path s which is still possible in the installed state.
Anstelle einer am Deckel 2 befestigten Führungsschiene 8 zur Aufnahme der Einspannelemente 10 kann auch ein am oberen Bund 7 des Reaktorschachtes 6 angeordnete Führungs¬ schiene 8 vorgesehen sein. In einer weiteren Ausführungs¬ form können auch Einspannelemente vorgesehen sein, die in segmentartigen Führungsleisten gekapselt sind, die in den für die Kompensatorrohrsegmente vorgesehenen Positionen lösbar mit dem oberen Bund 7 des Reaktorschachtes 6 ver¬ bunden werden. Das Zustandekommen des maximal möglichen Arbeitsweges s ist aus der Darstellung gemäß Figur 2 ersichtlich. Dort wird der Arbeitsweg s durch einen mit dem Reaktorschacht verschraubten kuppeiförmigen mechanischen Anschlag 30 bewirkt.Instead of a guide rail 8 fastened to the cover 2 for receiving the clamping elements 10, a guide rail 8 arranged on the upper collar 7 of the reactor shaft 6 can also be provided. In a further embodiment, clamping elements can also be provided which are encapsulated in segment-like guide strips which are releasably connected to the upper collar 7 of the reactor shaft 6 in the positions provided for the compensator tube segments. The formation of the maximum possible travel s can be seen from the illustration in FIG. 2. There, the work path s is effected by a dome-shaped mechanical stop 30 screwed to the reactor shaft.
In Figur 3 ist zu erkennen, daß am Stützbund 4 mehrere Ringschienen 8 segmentartig vorgesehen sind, auf die je¬ weils eine Vielzahl von Einspannelementen 10 aufgeschoben ist. Diese Einspannelemente 10 sind voneinander unab¬ hängig und lösbar mit der am Stützbund 4 fixierten Füh¬ rungsschiene 8 verbundene Einheiten, die unabhängig von¬ einander geprüft und im Bedarfsfall problemlos einzeln ausgetauscht werden können.In FIG. 3 it can be seen that a plurality of ring rails 8 are provided in segment-like fashion on the support collar 4, onto each of which a large number of clamping elements 10 are pushed. These clamping elements 10 are independent of one another and detachably connected to the guide rail 8 fixed to the support collar 4, which are checked independently of one another and, if necessary, can be individually replaced without any problems.
In entsprechender Weise sind auch gemäß Figur 4 mehrere segmentförmige Basisleisten 9 vorgesehen, die entsprechend der Anzahl der Einspannelemente 10 mit balligen Ausfor¬ mungen 91. versehen sind. In der Figur sind außerdem die zwischen den einzelnen Basisleisten 9 angeordneten mecha¬ nischen Anschläge 30 zu erkennen. In a corresponding manner, a plurality of segment-shaped base strips 9 are also provided according to FIG. 4, which have spherical shapes 91 corresponding to the number of clamping elements 10 . are provided. The mechanical stops 30 arranged between the individual base strips 9 can also be seen in the figure.

Claims

Patentansprüche Claims
1. Anordnung zum Einspannen eines in einem Reaktordruckbe¬ hälter (1) angeordneten Reaktorschachtes (6), bei' der zwischen einem oberen Bund (7) des Reaktorschachtes (6) und dem Deckel (2) des Reaktordruckbehälters (1) eine Vielzahl parallelgeschalteter federnder Einspannelemente (10) vorgesehen ist, die derart angeordnet sind, daß innerhalb eines vorgegebenen Arbeitsweges (s) nur eine elastische Verformung dieser Einspannelemente (10) möglich ist.1. An arrangement for clamping a container in a Reaktordruckbe¬ (1) arranged in the reactor shaft (6), wherein 'between an upper collar (7) of the reactor shaft (6) and the lid (2) of the reactor pressure vessel (1) has a plurality of parallel-connected resilient Clamping elements (10) are provided which are arranged in such a way that only an elastic deformation of these clamping elements (10) is possible within a predetermined working path (s).
2. Anordnung nach Anspruch 1, d a d u r c h e¬ k e n n z e i c h n e t , daß zur Begrenzung des Arbeitsweges (s) am oberen Bund (7) des Reaktorschachtes (6) ein mechanischer Anschlag (30) angeordnet ist.2. Arrangement according to claim 1, that a mechanical stop (30) is arranged on the upper collar (7) of the reactor shaft (6) in order to limit the working path (s).
3. Anordnung nach einem der vorhergehenden Ansprüche, d a d u r c h g e k e n n z e i c h n e t , daß am Deckel (2) des Reaktordruckbehälters (1) oder am oberen Bund (7) des Reaktorschachtes (6) wenigstens eine Füh¬ rungsschiene (8) angeordnet ist, auf die die Einspann¬ elemente (10) aufgeschoben sind.3. Arrangement according to one of the preceding claims, characterized in that on the cover (2) of the reactor pressure vessel (1) or on the upper collar (7) of the reactor shaft (6) at least one guide rail (8) is arranged on which the Einspann¬ elements (10) are pushed on.
4. Anordnung nach Anspruch 3, d a d u r c h e¬ k e n n z e i c h n e t , daß die Einspannelemente (10) jeweils einen federnd gelagerten Druckstempel (14) mit einer konvexen Stirnfläche (141) umfassen, der sich mit dieser Stirnfläche (141) auf einer mit konkaven Ausfor¬ mungen (91) versehenen, am oberen Bund (7) des Reaktor¬ schachtes (6) bzw. am Deckel (2) des Reaktordruckbehäl¬ ters (1) angeordneten Basisleiste (9) abstützt. 4. Arrangement according to claim 3, dadurche¬ indicates that the clamping elements (10) each comprise a resiliently mounted pressure ram (14) with a convex end face (141) which with this end face (141) on a concave Ausfor¬ formations ( 91) provided on the upper collar (7) of the reactor shaft (6) or on the cover (2) of the reactor pressure vessel (1).
5. Anordnung nach Anspruch 4, d a d u r c h e¬ k e n n z e i c h n e t , daß die Einspannelemente (10) jeweils eine auf der Führungsschiene. aufschiebbare Führungshülse (12) für den Druckstempel (14) umfassen, die mit einem mechanischen Anschlag (121) für den Druckstempel (14) versehen ist.5. Arrangement according to claim 4, that the clamping elements (10) each have one on the guide rail. slide-on guide sleeve (12) for the pressure stamp (14), which is provided with a mechanical stop (121) for the pressure stamp (14).
6. Anordnung nach einem der Ansprüche 4 oder 5, d a- d u r c h g e k e n n z e i c h n e t, daß zur federnden Lagerung des Druckstempels (14) wenigstens eine Tellerfeder (16) vorgesehen ist, die wenigstens mittelbar zwischen der Führungsschiene (8) und dem Druckstempel (14) eingespannt ist.6. Arrangement according to one of claims 4 or 5, d a- characterized in that at least one plate spring (16) is provided for the resilient mounting of the pressure stamp (14), which is clamped at least indirectly between the guide rail (8) and the pressure stamp (14) is.
7. Reaktordruckbehälter (1) mit einem Deckel (2) und einem in seinem Innern angeordneten und gegen den Deckel (2) verspannten Reaktorschacht (6), g e k e n n z e i c h n e t durch eine Anordnung gemäß einem der vorhergehenden Ansprüche. 7. reactor pressure vessel (1) with a lid (2) and a reactor shaft (6) arranged inside it and braced against the lid (2), g e k e n n z e i c h n e t by an arrangement according to one of the preceding claims.
PCT/DE1993/001004 1992-11-10 1993-10-21 Arrangement for clamping a reactor shaft arranged in a reactor pressure vessel WO1994011881A1 (en)

Priority Applications (2)

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UA95048346A UA27940C2 (en) 1992-11-10 1993-10-21 РПаЎ±б
RU95110056/06A RU2144705C1 (en) 1992-11-10 1993-10-21 Clamping device for reactor cavity mounted in reactor pressure tank

Applications Claiming Priority (2)

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DE9215253U DE9215253U1 (en) 1992-11-10 1992-11-10 Arrangement for clamping a reactor shaft arranged in a reactor pressure vessel
DEG9215253.8U 1992-11-10

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WO1994011881A1 true WO1994011881A1 (en) 1994-05-26

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PCT/DE1993/001004 WO1994011881A1 (en) 1992-11-10 1993-10-21 Arrangement for clamping a reactor shaft arranged in a reactor pressure vessel

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CZ (1) CZ281741B6 (en)
DE (1) DE9215253U1 (en)
RU (1) RU2144705C1 (en)
UA (1) UA27940C2 (en)
WO (1) WO1994011881A1 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5797015A (en) * 1995-04-18 1998-08-18 Pitney Bowes Inc. Method of customizing application software in inserter systems
CN103470668A (en) * 2012-06-08 2013-12-25 中国核动力研究设计院 Compound annular spring with large compensation rate

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5918489A (en) * 1982-07-23 1984-01-30 株式会社東芝 Reactor container
DD220408A1 (en) * 1983-09-01 1985-03-27 Schiffbau Veb K HYDRAULIC FORCE MEASURING DEVICE
EP0138477A1 (en) * 1983-09-30 1985-04-24 Westinghouse Electric Corporation Improved reactor internals hold down spring
EP0428433A1 (en) * 1989-11-15 1991-05-22 Framatome Device for fixation of upper spider guide plate in a nuclear reactor vessel

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4096034A (en) * 1976-12-16 1978-06-20 Combustion Engineering, Inc. Holddown structure for a nuclear reactor core
DE2921750C2 (en) * 1979-05-29 1987-01-29 Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund Device for supporting the core of a nuclear reactor on a component adjacent to the core
DE3326207A1 (en) * 1983-07-21 1985-01-31 Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund Retaining and clamping device for a cave cover on a prestressed concrete vessel

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5918489A (en) * 1982-07-23 1984-01-30 株式会社東芝 Reactor container
DD220408A1 (en) * 1983-09-01 1985-03-27 Schiffbau Veb K HYDRAULIC FORCE MEASURING DEVICE
EP0138477A1 (en) * 1983-09-30 1985-04-24 Westinghouse Electric Corporation Improved reactor internals hold down spring
EP0428433A1 (en) * 1989-11-15 1991-05-22 Framatome Device for fixation of upper spider guide plate in a nuclear reactor vessel

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
DATABASE WPI Week 8410, Derwent World Patents Index; AN 84-059887 *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5797015A (en) * 1995-04-18 1998-08-18 Pitney Bowes Inc. Method of customizing application software in inserter systems
CN103470668A (en) * 2012-06-08 2013-12-25 中国核动力研究设计院 Compound annular spring with large compensation rate

Also Published As

Publication number Publication date
CZ115395A3 (en) 1995-09-13
UA27940C2 (en) 2000-10-16
RU95110056A (en) 1997-06-20
DE9215253U1 (en) 1994-03-17
RU2144705C1 (en) 2000-01-20
CZ281741B6 (en) 1997-01-15

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