Development and evaluation of welding repair for threaded hole of Reactor Pressure Vessel flange

Author:

Huang TengfeiORCID,Jin Liang,Chen Tao,Qiu Zhensheng

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference29 articles.

1. Research on repair scheme of reactor pressure vessel flange stud hole;Zhou;Press. Vessel Technol.,2015

2. Nondestructive Evaluation Reactor Pressure Vessel Threads in Flange Examination Requirements;Moody,2016

3. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety PWR Pressure Vessels;Banic,1999

4. Watts bar nuclear plant unit 2 construction - NRC integrated inspection report 05000391/2012604 [letter];Robert,2012

5. French Association for Design, Construction and In-Service Inspection Rules for Nuclear Island Components (AFCEN). Design and Construction Rules for Mechanical Components of PWR Nuclear Islands (RCC-M). 2000 Version and 2002 Addendum,2002

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