TW363193B - Method and apparatus for repairing boiling water reactor shrouds - Google Patents

Method and apparatus for repairing boiling water reactor shrouds

Info

Publication number
TW363193B
TW363193B TW083110610A01A TW083110610A01A TW363193B TW 363193 B TW363193 B TW 363193B TW 083110610A01 A TW083110610A01 A TW 083110610A01A TW 083110610A01 A TW083110610A01 A TW 083110610A01A TW 363193 B TW363193 B TW 363193B
Authority
TW
Taiwan
Prior art keywords
shroud
longitudinal members
tie
repairing
preload
Prior art date
Application number
TW083110610A01A
Other languages
Chinese (zh)
Inventor
Sterling J Weems
Noman Cole
Harold W Mccurdy
Original Assignee
Mpr Associates Inc
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
Priority claimed from US08/358,085 external-priority patent/US5600689A/en
Application filed by Mpr Associates Inc filed Critical Mpr Associates Inc
Application granted granted Critical
Publication of TW363193B publication Critical patent/TW363193B/en

Links

Classifications

    • 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

  • Working Measures On Existing Buildindgs (AREA)

Abstract

A method and apparatus for repairing nuclear reactor core shrouds includes applying vertical compressive forces to the shroud in situ to urge opposed ends of the shroud toward one another using a plurality of tie-rods, each including a plurality of coaxial longitudinal members separated by a radial gap filled with reactor coolant or some other damping fluid. One of the longitudinal members is secured to upper and lower portions of the shroud for maintaining a sufficient preload to hold the shroud together and is coupled with one or more other longitudinal members in a manner to transmit axial loads thereto upon extending a predetermined axial distance. A plurality of radial spacers can also be positioned at longitudinally spaced locations along the length of the tie-rod to assure control rod insertion by limiting lateral movement of the shroud and can reduce the preload required for preventing the formation of new cracks and stabilizing existing cracks.
TW083110610A01A 1994-12-15 1995-10-03 Method and apparatus for repairing boiling water reactor shrouds TW363193B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US08/358,085 US5600689A (en) 1994-02-02 1994-12-15 Method and apparatus for repairing boiling water reactor shrouds utilizing tie-rods with multiple longitudinal members

Publications (1)

Publication Number Publication Date
TW363193B true TW363193B (en) 1999-07-01

Family

ID=57940863

Family Applications (1)

Application Number Title Priority Date Filing Date
TW083110610A01A TW363193B (en) 1994-12-15 1995-10-03 Method and apparatus for repairing boiling water reactor shrouds

Country Status (1)

Country Link
TW (1) TW363193B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
TWI407454B (en) * 2008-03-15 2013-09-01 Areva Gmbh An apparatus for the repairs of damaged portions within a wall range under water of a vessel or a sink
TWI846874B (en) * 2019-05-16 2024-07-01 美商弗拉馬東公司 Nuclear reactor core shroud securing device

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
TWI407454B (en) * 2008-03-15 2013-09-01 Areva Gmbh An apparatus for the repairs of damaged portions within a wall range under water of a vessel or a sink
TWI846874B (en) * 2019-05-16 2024-07-01 美商弗拉馬東公司 Nuclear reactor core shroud securing device

Similar Documents

Publication Publication Date Title
DE69601690T2 (en) Device and method for jointly storing nuclear fuel bundles and control rods
DE2354540C2 (en) Reflector inserted between the thermal shield and the core of a reactor
ES8701417A1 (en) Method and device for reconstruction of nuclear fuel assemblies
DE69502527T2 (en) Nuclear reactor vessel with built-in retention system and retention system setting procedure
CN108385539A (en) Across the arch ring long range push construction method of Deck Arch Bridges Steel Concrete composite beam
TW363193B (en) Method and apparatus for repairing boiling water reactor shrouds
DE1223466B (en) Fuel element bundle for gas-cooled nuclear reactors operated at high temperature
DE69014471T2 (en) Guide mast for nuclear reactor charger.
WO2005034137A3 (en) Nuclear fuel assembly comprising an internal reinforcement device
DE1559292A1 (en) Prestressed concrete pressure vessel, especially for nuclear reactors and processes for its manufacture
DE1564186A1 (en) Support floor in a pebble bed reactor
DE2236026C3 (en) Pressure vessel for high internal pressures and high temperatures, in particular for holding nuclear power plant components and method for erecting a pressure vessel
DE3042552A1 (en) Pebble bed reactor side reflector - has block arranged to give uneven inner face thus reducing retarding effect
DE3221860C2 (en) Support device on a pressure vessel, in particular a reactor pressure vessel, against horizontal forces
DE1055141B (en) Fuel element for a heterogeneous nuclear reactor
DE2020046A1 (en) Holder for a certain amount of meltable material in a solid state in a condenser chamber
DE1221370B (en) Pressure vessel for a nuclear reactor
DE1514999A1 (en) Fuel assembly with heat shield
CH627825A5 (en) Process for producing a reinforced-concrete structure and climbing shuttering for carrying out the process
DE3601748C2 (en)
DE19947120C2 (en) Process for preparing a fuel assembly for final storage and prepared fuel assembly
DE1684918A1 (en) Pre-stressed concrete protective jacket and process for its manufacture
DE3506677A1 (en) Method for the reinforcement of concrete transmission towers
DE2130589A1 (en) Method of fueling a nuclear reactor
DE1764258C3 (en) Nuclear reactor with gas cooling