Abstract

This paper summarizes the effects of interactions between interstitial impurity atoms and radiation produced defects on the mechanical and fracture characteristics of ferritic steels. It emphasizes radiation embrittlement and pressurized thermal shock phenomena associated with pressure boundary materials in light water reactors. Evidence is presented for the existence of strain-aging in pressure vessel steels. Also examined are earlier results on controlled neutron irradiation experiments on iron and mild steel, the author’s recent work on radiation effects in low carbon mild steel and the behavior of nuclear pressure vessel steel. Relevant results obtained at NC State (USA), Aktiebola-get Atomenergi (Sweden), AERE (UK) and BARC (India) are reviewed.

Full Text
Published version (Free)

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call