Inderscience Publishers

A historical review of WWER RPV embrittlement issues

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The paper tries to describe the history of the radiation effects study in WWER type reactor pressure vessels – from their design, manufacturing and operation point of view. The paper shows the time evolution and also institutions that were and are included in this research and development study. Main effort has been concentrated on development and realisation of steels and welding joint with low susceptibility to radiation damage as neutron fluences on reactor pressure wall in WWER type reactors are relatively high.

Keywords: reactor pressure vessels, RPV steels, radiation embrittlement, WWER type reactors, 15Kh2MFA type steel, 15Kh2NMFA type steel, annealing, nuclear reactors, RPV materials, RPV embrittlement, welding joints, radiation damage, neutron fluences

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