Method for producing, from a preform made of austenitic stainless steel with a low carbon content, a wear-resistant and corrosion-resistant cladding for a nuclear reactor, corresponding cladding and corresponding control cluster

US9914986B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-9914986-B2
Application numberUS-201214348378-A
CountryUS
Kind codeB2
Filing dateSep 28, 2012
Priority dateSep 30, 2011
Publication dateMar 13, 2018
Grant dateMar 13, 2018

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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  6. CPC / IPC classifications

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  7. Citations and related patents

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Abstract

Official abstract text for this publication.

A method for producing a wear-resistant and corrosion-resistant stainless steel part for a nuclear reactor is provided. This method includes steps of providing a tubular blank in austenitic stainless steel whose carbon content is equal to or lower than 0.03% by weight; shaping the blank; finishing the blank to form the cladding; hardening the outer surface of the cladding by diffusing one or more atomic species; the blank, before the providing step or during the shaping or finishing step, being subjected to at least one hyper quenching with sub-steps of: heating the blank to a sufficient temperature and for a sufficient time to solubilize any precipitates present; quenching the blank at a rate allowing the austenitic structure to be maintained in a metastable state at ambient temperature and free of precipitates.

First claim

Opening claim text (preview).

The invention claimed is: 1. A method for manufacturing a cladding resistant to wear and corrosion for nuclear reactor, comprising: providing a tubular blank in austenitic stainless steel whose carbon content is equal to or lower than 0.03% by weight; shaping the blank; finishing the blank to form the cladding; and hardening an outer surface of the cladding by diffusing one or more atomic species; the blank, before the providing step or during the shaping or finishing step, being subjected to at least one hyper quenching with sub-steps of: heating the blank to a sufficient temperature and for a sufficient time to solubilise any precipitates present; and quenching the blank from the quench start temperature down to lower then 850° C. in less than 3 min allowing the austenitic structure to be maintained in a metastable state at ambient temperature and free of precipitates. 2. The method as recited in claim 1 wherein the heating sub-step is conducted at a temperature between 1020° C. and 1100° C. 3. The method as recited in claim 2 wherein the heating sub-step is conducted at a temperature between 1040 and 1080° C. 4. The method as recited in claim 1 wherein the heating sub-step is conducted for a time of between 1 minute 30 seconds and 30 minutes. 5. The method as recited in claim 4 wherein the heating sub-step is conducted for a time of between 3 and 10 minutes. 6. The method as recited in claim 1 wherein during the quench sub-step the blank is cooled from the quench start temperature down to lower than 450° C. in less than one quarter of an hour. 7. The method as recited in claim 1 wherein the hyper quenching is not followed during the shaping step or during the finishing step by an operation creating surface tensile stresses. 8. The method as recited in claim 1 wherein the hyper quenching is not followed during the shaping step or during the finishing step by grinding, brushing, polishing or buffing. 9. The method as recited in claim 1 wherein the finishing step comprises at least one stripping or tribo-finishing of the outer surface of the cladding. 10. The method as recited in claim 1 wherein the hardening step of the outer surface of the cladding comprises plasma nitriding. 11. The method as recited in claim 10 wherein the hardening step of the outer surface of the cladding comprises carbonitriding or nitrocarburizing. 12. The method as recited in claim 1 wherein the hardening step comprises carburizing or case hardening. 13. The method as recited in claim 1 wherein the blank is not welded. 14. A cladding in austenitic stainless steel obtained by the method as recited in claim 1 . 15. A control cluster for pressurized water nuclear reactor comprising: a spider structure and absorber rods carried by the spider, the absorber rods comprising claddings containing at least one neutron-absorbing material and end plugs closing the claddings, wherein the claddings of at least some of the absorber rods are the cladding as recited in claim 14 .

Assignees

Inventors

Classifications

  • during manufacturing of tubular bodies · CPC title

  • Construction of control elements · CPC title

  • After-treatment · CPC title

  • by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section · CPC title

  • C21D1/72Primary

    during chemical change of surfaces · CPC title

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What does patent US9914986B2 cover?
A method for producing a wear-resistant and corrosion-resistant stainless steel part for a nuclear reactor is provided. This method includes steps of providing a tubular blank in austenitic stainless steel whose carbon content is equal to or lower than 0.03% by weight; shaping the blank; finishing the blank to form the cladding; hardening the outer surface of the cladding by diffusing one or mo…
Who is the assignee on this patent?
Areva Np
What technology area does this patent fall under?
Primary CPC classification C21D1/72. Mapped technology areas include Chemistry & Metallurgy.
When was this patent published?
Publication date Tue Mar 13 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).