Fracture in ferritic reactor steel - Dynamic strain aging and cyclic loading

Citation
Kl. Murty et Cc. Seok, Fracture in ferritic reactor steel - Dynamic strain aging and cyclic loading, JOM-J MIN, 53(7), 2001, pp. 23-26
Citations number
24
Categorie Soggetti
Metallurgy
Journal title
JOM-JOURNAL OF THE MINERALS METALS & MATERIALS SOCIETY
ISSN journal
10474838 → ACNP
Volume
53
Issue
7
Year of publication
2001
Pages
23 - 26
Database
ISI
SICI code
1047-4838(200107)53:7<23:FIFRS->2.0.ZU;2-Y
Abstract
Ferritic steels commonly used for pressure vessels and reactor supports in light water reactors exhibit dynamic strain aging resulting in decreased du ctility and tough ness. In addition, recent work indicated decreased toughn ess during reverse-cyclic loading that has implications on reliability of t hese structures under seismic loading conditions, This paper summarizes the authors recent work on these aspects, along with synergistic effects of in terstitial impurity atoms and radiation-induced point defects, which result in interesting beneficial effects of radiation exposure at appropriate tem perature and strain-rate conditions. While the cyclic loading effects on to ughness are studied in A516 steel, the dynamic strain aging and radiation-d efect interactions were investigated on pure iron as well as several ferrit ic steels. In addition, studies on fast vs. total (thermal+fast) neutron sp ectra revealed unexpected results due to the influence of radiation exposur e on source hardening component of the yield stress; grain size of pure iro n plays a significant role in these effects. The paper concludes with futur e research needed to address these concerns.