PSI - Issue 16

Peter Trampus / Procedia Structural Integrity 16 (2019) 161–168

168

Peter Trampus / Structural Integrity Procedia 00 (2019) 000 – 000

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Fig. 5. RPV cladding ET qualification test block.

Acknowledgement

The author would like to express his thanks to the managers and experts of Paks NPP providing the opportunity to be involved in many of NDE related activities and analyses.

References

ASME, 2001. ASME Boiler and Pressure Vessel Code. Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components, ASME, New York. ENIQ, 2005. European Framework Document for Risk-informed In-service Inspection, ENIQ Report nr. 23, EUR 21581 EN, European Commission. IAEA, 2017. Nuclear Technology Review 2017, International Atomic Energy Agency, Vienna. IAEA, 2018. Improvement of Effectiveness of In-Service Inspection in Nuclear Power Plants, IAEA-TECDOC-1853, International Atomic Energy Agency, Vienna. Trampus, P., 2010. PLIM for Paks. Nuclear Engineering International, April 34 – 38. Trampus, P., Babics, P. P., 2016. Comprehensive Adaptation of the ASME Code at Paks NPP, Hungary, in “Global Applications of the ASME Boiler & Pressure Vessel Code” K. K. Rao (Ed.). The American Society of Mechanical Engineers, New York. Trampus, P., 2018. Pressurized Thermal Shock analysis of the reactor pressure vessel. Procedia Structural Integrity, 13, 2083 – 2088 Whittle, M. J., 2009. A review of worldwide practice and experience in the qualification of ultrasonic inspections of nuclear components over the past two decades. Insight 51, 140 – 150.