Effects of process-generated hydrogen on RPV walls

Bibliography

[1] Electrabel GDF SUEZ. Safety case report: Doel 3. Technical Report December, Electrabel GDF SUEZ, 2012. [2] Noaki Soneda. Irradiation embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants . Woodhead Publishing, 2015. [3] IAEA. Deterministic Safety Analysis for Nuclear Power Plants . IAEA, Vienn, 2009. [4] FANC, 2016. [5] Iron & Steel Society. Steel Products Manual Stainless Steels . Warrendale, 1999. [6] FANC. Doel 3 and Tihange 2 reactor pressure vessels: Provisional evaluation report. Technical report, FANC, 2013. [7] FANC. Flaw indications in the reactor pressure vessel of Doel 3. Technical Report September, FANC, 2012. [8] ASME Boiler and Pressure Vessel Code, Section XI . American Society of Mechanical Engineers, New York. [9] Eric Van Walle. Nuclear Materials 2 Reactor Pressure Vessel Integrity Assess- ment, 2016. [10] L Hernandez, J C Barbant, Ph Bastin, and T Pasquier. Characterization of Crack-Like Sub-Surface Defect Located in Nuclear Reactor Core Region. In 15th World Conference on Non-Destructive Testing , Roma, 2000. [11] Nicolas Verdiere, Pierre Cambefort, Karim Zamoum, Karl Payraudeau, and Sebastien Royer. Life Assessment of Components With Underclad Cracks in PWR. In ASME/JSME 2004 Pressure Vessels and Piping Conference , pages 93–96, San Diego, 2004. ASME. [12] F Balestreri, B Monnot, G Cattiaux, and I Delvallee. Assessment of the RPVs for long term operation in France. In IAEA Technical Meeting on Degradation of Primary Components of Pressurized Water Cooled Nuclear Power Plants: Current Issues and Future Chal lenges , Vienna, 2013. IAEA. 121

Made with FlippingBook Publishing Software