WO1997034303A1 - Recipient de coeur de reacteur pour cuve de reacteur nucleaire, et procede de montage associe - Google Patents

Recipient de coeur de reacteur pour cuve de reacteur nucleaire, et procede de montage associe Download PDF

Info

Publication number
WO1997034303A1
WO1997034303A1 PCT/EP1997/001010 EP9701010W WO9734303A1 WO 1997034303 A1 WO1997034303 A1 WO 1997034303A1 EP 9701010 W EP9701010 W EP 9701010W WO 9734303 A1 WO9734303 A1 WO 9734303A1
Authority
WO
WIPO (PCT)
Prior art keywords
holding structure
flange
pressure vessel
core container
reactor pressure
Prior art date
Application number
PCT/EP1997/001010
Other languages
German (de)
English (en)
Inventor
Gerd Reimer
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 EP97905134A priority Critical patent/EP0886868A1/fr
Priority to JP09532238A priority patent/JP2000510577A/ja
Publication of WO1997034303A1 publication Critical patent/WO1997034303A1/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
    • G21C5/10—Means for supporting the complete structure
    • 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 a core container for a reactor pressure container of a nuclear reactor plant and to a method for its assembly.
  • the invention is based on the object of specifying a core container for a reactor pressure vessel and a method for its assembly, in which the assembly is facilitated and which are mounted largely tension-free on a remaining lower part of the removed core vessel remaining in the reactor pressure vessel can.
  • the invention is also based on the object of specifying a method for assembling the core container.
  • the second object is achieved with the features of claim 5.
  • the core container contains an annular flange with which it rests on a holding structure fixed in the reactor pressure vessel, means on the flange being provided for displacing and fixing its position relative to the holding structure.
  • the flange can be fixed to the new core container before it is mounted on the holding structure.
  • the end face of the flange has a circumferential U-shaped groove which imparts the free end of the holding structure facing it.
  • a further embodiment of the invention is to push Ver ⁇ and fixing the position of the flange relative to the te Modell Hal ⁇ at least one side wall of the groove with a through hole for 'recording provided a pressable against the support structure Anstellelementes.
  • a socket screwed into the through bore is provided as the adjusting element.
  • annular flange is placed on an annular holding structure fixed in the reactor pressure container, the position of which is adjusted relative to the holding structure and fixed in a predetermined position.
  • the core container is then placed and fixed on this adjusted and fixed flange.
  • the flange is preferably pushed onto the free end of the holding structure facing it with a circumferential u-shaped groove arranged in its end face.
  • an essentially annular holding structure 4 is arranged in the reactor pressure vessel 2, which is firmly connected to it.
  • This holding structure 4 is concerned in the exemplary embodiment is a lower part of an old core container remaining in the reactor pressure vessel 2.
  • annular or cylindrical holding structure 4 there is a new core container 6, which is provided in its lower part with an annular flange 8 which has a circumferential u-shaped groove 10 on its end face facing the holding structure 4.
  • This groove 10 receives the free end of the holding structure 4 facing it, so that the flange 8 rests with the base 12 of its groove 10 on the end face of the cylindrical holding structure 4.
  • the width of the groove 10 is dimensioned such that the flange 8 can be pushed onto the holding structure 4 even if the flange 8 or the holding structure 4 is out of round.
  • the core container 6 is firmly connected to the flange 8, for example screwed.
  • This screw connection is preferably carried out only after the flange 8 has been mounted on the holding structure 4, since it is easier to adjust in the holding structure 4 than the entire component in the preassembled state.
  • the side walls 14 and 16 of the groove 10 are each provided with a radial through bore 18, which are coaxial to one another and each provided with a thread for receiving an adjusting element 20, in the exemplary embodiment a bushing.
  • the flange 8 can then be displaced into a predetermined position transversely to its central axis because of the play in the groove 10.
  • a measuring cross is hooked into the flange 8, which is brought into line with measuring points previously introduced in the reactor pressure vessel 2 and a correct positioning of the flange 8 and thus also afterwards Assured new core container 6 in the reactor pressure vessel 2 guaranteed.
  • the adjusting elements 20 are pressed onto the holding structure 4 with a predetermined setting torque and secured with a dowel pin or a dowel screw 22.
  • the flange 8 is then screwed to the holding structure 4.
  • the new core container is then inserted, screwed to the flange 8 and clamped in the reactor pressure container.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Pressure Vessels And Lids Thereof (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Un récipient de coeur de réacteur (6) destiné à une cuve de réacteur (2) d'une centrale nucléaire contient un flasque annulaire (8), par lequel il repose sur une structure support (4) fixée dans la cuve (2). Le flasque (8) comporte un système permettant de modifier et de fixer sa position par rapport à la structure support (4).
PCT/EP1997/001010 1996-03-11 1997-02-28 Recipient de coeur de reacteur pour cuve de reacteur nucleaire, et procede de montage associe WO1997034303A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
EP97905134A EP0886868A1 (fr) 1996-03-11 1997-02-28 Recipient de coeur de reacteur pour cuve de reacteur nucleaire, et procede de montage associe
JP09532238A JP2000510577A (ja) 1996-03-11 1997-02-28 原子炉設備の原子炉圧力容器の炉心容器とその組立方法

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19609343.0 1996-03-11
DE19609343A DE19609343C1 (de) 1996-03-11 1996-03-11 Kernbehälter für einen Reaktordruckbehälter einer Kernreaktoranlage und Verfahren zu seiner Montage

Publications (1)

Publication Number Publication Date
WO1997034303A1 true WO1997034303A1 (fr) 1997-09-18

Family

ID=7787838

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/EP1997/001010 WO1997034303A1 (fr) 1996-03-11 1997-02-28 Recipient de coeur de reacteur pour cuve de reacteur nucleaire, et procede de montage associe

Country Status (4)

Country Link
EP (1) EP0886868A1 (fr)
JP (1) JP2000510577A (fr)
DE (1) DE19609343C1 (fr)
WO (1) WO1997034303A1 (fr)

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB903480A (en) * 1960-06-14 1962-08-15 Atomic Energy Authority Uk Improvements in or relating to pressure vessels such as pressure vessels suitable for nuclear reactors
JPS607387A (ja) * 1983-06-28 1985-01-16 株式会社東芝 原子炉炉心支持構造
US4657730A (en) * 1983-10-28 1987-04-14 Westinghouse Electric Corp. Low stressed rationally shaped core support
US4756877A (en) * 1985-11-06 1988-07-12 Westinghouse Electric Corp. Core barrel support system for nuclear reactors
US5265141A (en) * 1992-08-19 1993-11-23 General Electric Company Captive fastener
JPH0886896A (ja) * 1994-09-16 1996-04-02 Toshiba Corp 原子炉内シュラウドならびにその据付方法および交換方法
US5519744A (en) * 1994-12-06 1996-05-21 General Electric Company Removable shroud and pump deck for a boiling water nuclear reactor
US5583899A (en) * 1995-01-17 1996-12-10 General Electric Company Removable retrofit shroud for a boiling water nuclear reactor and associated method

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB903480A (en) * 1960-06-14 1962-08-15 Atomic Energy Authority Uk Improvements in or relating to pressure vessels such as pressure vessels suitable for nuclear reactors
JPS607387A (ja) * 1983-06-28 1985-01-16 株式会社東芝 原子炉炉心支持構造
US4657730A (en) * 1983-10-28 1987-04-14 Westinghouse Electric Corp. Low stressed rationally shaped core support
US4756877A (en) * 1985-11-06 1988-07-12 Westinghouse Electric Corp. Core barrel support system for nuclear reactors
US5265141A (en) * 1992-08-19 1993-11-23 General Electric Company Captive fastener
JPH0886896A (ja) * 1994-09-16 1996-04-02 Toshiba Corp 原子炉内シュラウドならびにその据付方法および交換方法
US5519744A (en) * 1994-12-06 1996-05-21 General Electric Company Removable shroud and pump deck for a boiling water nuclear reactor
US5583899A (en) * 1995-01-17 1996-12-10 General Electric Company Removable retrofit shroud for a boiling water nuclear reactor and associated method

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN vol. 096, no. 8 2 April 1996 (1996-04-02) *
PATENT ABSTRACTS OF JAPAN vol. 85, no. 09 16 January 1985 (1985-01-16) *

Also Published As

Publication number Publication date
EP0886868A1 (fr) 1998-12-30
JP2000510577A (ja) 2000-08-15
DE19609343C1 (de) 1997-09-11

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