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PWSCC and System Engineering Development of Internal Inspection and Maintenance Methodology for RCS

  • Abdallah, Khaled Atya Ahmed (Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School) ;
  • Mesquita, Patricia Alves Franca de (Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School) ;
  • Yusoff, Norashila (Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School) ;
  • Nam, GungIhn (Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School) ;
  • Jung, JaeCheon (Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School) ;
  • Lee, YoungKwan (Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School)
  • Received : 2015.11.18
  • Accepted : 2016.06.11
  • Published : 2016.06.30

Abstract

Due to safety of the plant, it became very clear the importance of study occurrence reactor coolant system (RCS) issues specially the primary water stress corrosion cracking (PWSCC). The Systems Engineering (SE) approach is characterized by the application of a structured engineering methodology for the design of a complex system or component. Robotic devices have been used for internal inspection, maintenance and performing remote welding and inspection in high-radiation areas. In this paper, PWSCC overview and inlay and over lay welding methodology introduced, concept of robotic device that can be inserted into the piping via Steam Generator (SG) main way to access to primary piping of pressurized water reactor (PWR) is developed based on SE methodology. A 3D model of the inspection system was developed along with the APR1400 (Advanced Power Reactor)reactor coolant systems (RCS) and internals with virtual 3D simulation of the operation for visualization to prove the validity of the concept.

Keywords

References

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