The revised second edition of this established text offers readers a significantly expanded
introduction to the effects of radiation on metals and alloys. It describes the various …

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 …

Energetic ions can be used to understand the effects of neutron irradiation on reactor
components while avoiding high residual radioactivity and the problem of finding suitable …

The concentration of chromium (Cr) plays an important role on the radiation induced
microstructure of the binary Fe–Cr alloys, in particular on the formation of cavities leading to …

Large amounts of hydrogen and helium are generated in structural metals in accelerator-
driven systems. It is shown that under certain conditions, hydrogen can be stored in …

Side-by-side irradiation of stoichiometric MgAl2O4 and α-Al2O3 in JOYO shows that the
radiation-induced microstructural evolution to exposure of≤ 6 dpa proceeds by very …

Abstract Ferritic Martensitic (F/M) steel HT9 specimens were irradiated in the Advanced Test
Reactor up to 4.16 dpa in three temperature ranges (roughly from 300 to 600° C). The post …

Contrary to the behavior of swelling of model fcc Fe–Cr–Ni alloys irradiated in the same
FFTF-MOTA experiment, model bcc Fe–Cr alloys do not exhibit a strong dependence of …

Titanium modified austenitic stainless steel 316 (Alloy D9) is the material of clad and
wrapper for the 500 MWe Prototype Fast Breeder Reactor (PFBR) at Kalpakkam, India …

An on-line instrumented material irradiation rig (MARICO-II) was used for investigating
temperature history effect for void swelling behavior in V-Fe binary alloys irradiated at a fast …