Nuclear reactor nozzle repair method

US10020080B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-10020080-B2
Application numberUS-201314655110-A
CountryUS
Kind codeB2
Filing dateDec 24, 2013
Priority dateDec 28, 2012
Publication dateJul 10, 2018
Grant dateJul 10, 2018

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  1. Title

    What the patent document calls the invention.

  2. Abstract

    A short plain-language summary of the technical disclosure.

  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

    The legal scope of protection — read this for what is actually claimed.

  6. CPC / IPC classifications

    Technology tags used to group this patent with similar filings.

  7. Citations and related patents

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Abstract

Official abstract text for this publication.

A nozzle repair method and a nuclear reactor vessel include: removing a trepanning portion ( 208 ) as a connection portion with respect to an in-core instrumentation cylinder ( 204 ) in a groove-welding portion ( 206 ); removing the in-core instrumentation cylinder ( 204 ) from a semi-spherical portion ( 66 ) as a lower end plate; forming a surface buttered-welding portion ( 210 ) by buttered-welding the surface of the groove-welding portion ( 206 ); forming a welding groove ( 212 ) by grooving the surface buttered-welding portion ( 210 ); inserting a new in-core instrumentation cylinder ( 204 A) provided with a circumferential groove portion ( 204 f ) outside an instrumentation equipment guide passage ( 204 d ) into an attachment hole ( 203 ); and fixing the new in-core instrumentation cylinder ( 204 A) by groove-welding the welding groove ( 212 ). Accordingly, since the nozzle welding area is suppressed to a predetermined range, the workability of the repair is improved.

First claim

Opening claim text (preview).

The invention claimed is: 1. A nozzle repair method for a nuclear reactor instrumentation nozzle comprising an in-core instrumentation cylinder inserted into an attachment hole in a semi-spherical portion of a nuclear reactor vessel and a groove-weld between an inner surface of the semi-spherical portion and an outer surface of the in-core instrumentation cylinder, the method comprising steps of: disconnecting the in-core instrumentation cylinder from the nuclear reactor vessel by severing the groove-weld therebetween; removing the in-core instrumentation cylinder from the semi-spherical portion; forming a surface buttered-welding portion by buttered-welding a surface of the groove-weld; forming a welding groove by grooving the surface buttered-welding portion; inserting a new in-core instrumentation cylinder provided with an instrumentation equipment guide passage and a groove portion into the attachment hole, the instrumentation equipment guide passage penetrating the new in-core instrumentation cylinder in an axial direction thereof, the groove portion being provided radially outside of and along a circumference of the instrumentation equipment guide passage, one end of the groove portion being opened in the axial direction; and fixing the new in-core instrumentation cylinder by groove-welding the welding groove to an outer circumference of the new in-core instrumentation cylinder. 2. The nozzle repair method according to claim 1 , wherein the step of forming the surface buttered-welding portion includes performing buttered-welding on an area extending from the surface of the groove-weld to the inner surface of the semi-spherical portion and to the attachment hole. 3. The nozzle repair method according to claim 1 , wherein after the step of forming the surface buttered-welding portion on the surface of the groove-weld, an inner surface of the attachment hole is machined. 4. The nozzle repair method according to claim 1 , wherein the welding groove is formed within an area of the groove-weld. 5. The nozzle repair method according to claim 1 , wherein the new in-core instrumentation cylinder includes a main body portion which is inserted into the attachment hole and in contact with an inner surface thereof, a support portion which is continuous to the upper end of the main body portion and has a diameter smaller than the main body portion, the instrumentation equipment guide passage which penetrates the main body portion and the support portion, and the groove portion of which the end is opened to a stepped portion between the main body portion and the support portion. 6. The nozzle repair method according to claim 1 , wherein a welding material used to fix the new in-core instrumentation cylinder to the semi-spherical portion is a material having higher stress corrosion cracking resistance than the welding material of the groove-weld.

Assignees

Inventors

Classifications

  • G21C13/036Primary

    the tube passing through the vessel wall, i.e. continuing on both sides of the wall · CPC title

  • Inspection or maintenance of pipe-lines or tubes in nuclear installations · CPC title

  • Cross-Sectional Technologies · mapped topic

  • Details of handling arrangements · CPC title

  • Assembling, maintenance or repair of reactor components (G21C3/334 takes precedence) · CPC title

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Frequently asked questions

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What does patent US10020080B2 cover?
A nozzle repair method and a nuclear reactor vessel include: removing a trepanning portion ( 208 ) as a connection portion with respect to an in-core instrumentation cylinder ( 204 ) in a groove-welding portion ( 206 ); removing the in-core instrumentation cylinder ( 204 ) from a semi-spherical portion ( 66 ) as a lower end plate; forming a surface buttered-welding portion ( 210 ) by buttered-w…
Who is the assignee on this patent?
Mitsubishi Heavy Ind Ltd
What technology area does this patent fall under?
Primary CPC classification G21C13/036. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Jul 10 2018 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 8 related publications on this page (citations in our corpus or others sharing the same primary CPC).