WO1994011881A1 - Agencement permettant de serrer un puits de reacteur place dans la cuve d'un reacteur - Google Patents

Agencement permettant de serrer un puits de reacteur place dans la cuve d'un reacteur 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
Authority
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)
English (en)
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/uk
Priority to RU95110056/06A priority patent/RU2144705C1/ru
Publication of WO1994011881A1 publication Critical patent/WO1994011881A1/fr

Links

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.

Landscapes

  • 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)
  • Particle Accelerators (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)

Abstract

L'invention concerne un agencement permettant de serrer un puits de réacteur (6) placé dans la cuve d'un réacteur (1) et contenant une pluralité d'éléments de serrage (10) élastiques montés en parallèle qui se trouvent entre une collerette (7) supérieure du puits de réacteur (6) et le couvercle (2) de la cuve du réacteur (1). Ces éléments de serrage (10) sont disposés de manière à ce qu'il n'y ait qu'une déformation élastique desdits éléments de serrage (10) à l'intérieur d'une course de travail (s) prédéfinie. Ce procédé assure des conditions de serrage stables sur de longues périodes. L'utilisation d'éléments de serrage (10) échangeables individuellement permet également de réduire la quantité de déchets radioactifs produits lorsqu'un éventuel échange s'impose.
PCT/DE1993/001004 1992-11-10 1993-10-21 Agencement permettant de serrer un puits de reacteur place dans la cuve d'un reacteur WO1994011881A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
UA95048346A UA27940C2 (uk) 1992-11-10 1993-10-21 Напірний бак реактора
RU95110056/06A RU2144705C1 (ru) 1992-11-10 1993-10-21 Устройство для зажима расположенного в напорном баке реактора шахтного ствола реактора

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE9215253U DE9215253U1 (de) 1992-11-10 1992-11-10 Anordnung zum Einspannen eines in einem Reaktordruckbehälter angeordneten Reaktorschachtes
DEG9215253.8U 1992-11-10

Publications (1)

Publication Number Publication Date
WO1994011881A1 true WO1994011881A1 (fr) 1994-05-26

Family

ID=6885837

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/DE1993/001004 WO1994011881A1 (fr) 1992-11-10 1993-10-21 Agencement permettant de serrer un puits de reacteur place dans la cuve d'un reacteur

Country Status (5)

Country Link
CZ (1) CZ281741B6 (fr)
DE (1) DE9215253U1 (fr)
RU (1) RU2144705C1 (fr)
UA (1) UA27940C2 (fr)
WO (1) WO1994011881A1 (fr)

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 (zh) * 2012-06-08 2013-12-25 中国核动力研究设计院 复合式大补偿量环形弹簧

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5918489A (ja) * 1982-07-23 1984-01-30 株式会社東芝 原子炉容器
DD220408A1 (de) * 1983-09-01 1985-03-27 Schiffbau Veb K Hydraulische kraftmessvorrichtung
EP0138477A1 (fr) * 1983-09-30 1985-04-24 Westinghouse Electric Corporation Ressort pour la fixation des éléments internes d'un réacteur
EP0428433A1 (fr) * 1989-11-15 1991-05-22 Framatome Dispositif de calage de la plaque supérieure de support des guides de grappes par rapport à la cuve d'un réacteur nucléaire

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
DE2921750A1 (de) * 1979-05-29 1980-12-11 Hochtemperatur Reaktorbau Gmbh Vorrichtung fuer die abstuetzung des kerns eines atomreaktors an einem dem kern benachbarten bauteil
DE3326207A1 (de) * 1983-07-21 1985-01-31 Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund Halte- und spannvorrichtung fuer einen kavernen-deckel an einem spannbetonbehaelter

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5918489A (ja) * 1982-07-23 1984-01-30 株式会社東芝 原子炉容器
DD220408A1 (de) * 1983-09-01 1985-03-27 Schiffbau Veb K Hydraulische kraftmessvorrichtung
EP0138477A1 (fr) * 1983-09-30 1985-04-24 Westinghouse Electric Corporation Ressort pour la fixation des éléments internes d'un réacteur
EP0428433A1 (fr) * 1989-11-15 1991-05-22 Framatome Dispositif de calage de la plaque supérieure de support des guides de grappes par rapport à la cuve d'un réacteur nucléaire

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 (zh) * 2012-06-08 2013-12-25 中国核动力研究设计院 复合式大补偿量环形弹簧

Also Published As

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

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