Materials for future nuclear energy systems must operate under more extreme conditions
than those in current Gen II or Gen III systems. These conditions include higher temperature …

Abstract High-entropy alloys (HEAs), based on equiatomic or near-equiatomic mixture of
usually four or more elements, have attracted considerable attention as there are indications …

Nuclear power currently provides about 13% of electrical power worldwide, and has
emerged as a reliable baseload source of electricity. A number of materials challenges must …

It is well-known that ferritic and ferritic/martensitic steels develop much less swelling than
austenitic steels during neutron or charged particle irradiation. The prevailing assumption is …

The temperature dependencies of true strain-hardening and plastic-instability properties are
investigated for austenitic stainless steels; including annealed 304, 316, 316LN, and 20 …

Current understanding of radiation-induced material changes that occur in light-water-
reactor (LWR) core components is critically reviewed and linked to intergranular failure …

A cold worked 316SS baffle bolt was extracted from the Tihange pressurized water reactor
and sectioned at three different positions. The temperature and dose at the 1-mm bolt head …

Localized deformation has emerged as a key factor in the crack initiation process for
irradiated steels, as cracks are observed to nucleate preferentially at these sites. Using high …

Structure–property relationships are the foundation of materials science and are essential
for predicting material response to driving forces, managing in-service material degradation …

A knowledge of the dimensional stability of reactor structural components, under irradiation
conditions, is of major importance in the design of thermal, fast, and fusion reactors. When …