TY - JOUR
T1 - Mechanical characterization of two low-activation chromium alloys in AS-received and heat-treated conditions
AU - Lucon, Enrico
AU - Van Walle, Eric
AU - Decréton, Marc
PY - 2001
Y1 - 2001
N2 - In recent years, within the fusion long-term programmes, attention has been devoted to the characterization of Chromium (Cr) alloys, in view of their elevated corrosion resistance, low activation properties and high-temperature mechanical strength. As part of the European Fusion Programme, an activity has been launched in 1999 with the aim of exploring the potential of Cr alloys as structural materials in fusion reactors, for example, as first wall or blanket materials. Recent investigations have focused attention on two commercially available materials: high-purity 99.7% Cr (DUCROPUR) and Cr alloyed with 5% Fe and 1%Y203 (DUCROLLOY), both of which have shown excellent low activation characteristics. The mechanical properties of these two alloys, in both asreceived and heat-treated conditions, have been characterized at SCK-CEN by means of tensile, instrumented impact and static three-point bend tests, using standard and sub-size specimens. Tensile tests have also been carried out on samples irradiated at 300 °C in the BR2 reactor in Mol up to an accumulated dose of about 0.5 dpa.
AB - In recent years, within the fusion long-term programmes, attention has been devoted to the characterization of Chromium (Cr) alloys, in view of their elevated corrosion resistance, low activation properties and high-temperature mechanical strength. As part of the European Fusion Programme, an activity has been launched in 1999 with the aim of exploring the potential of Cr alloys as structural materials in fusion reactors, for example, as first wall or blanket materials. Recent investigations have focused attention on two commercially available materials: high-purity 99.7% Cr (DUCROPUR) and Cr alloyed with 5% Fe and 1%Y203 (DUCROLLOY), both of which have shown excellent low activation characteristics. The mechanical properties of these two alloys, in both asreceived and heat-treated conditions, have been characterized at SCK-CEN by means of tensile, instrumented impact and static three-point bend tests, using standard and sub-size specimens. Tensile tests have also been carried out on samples irradiated at 300 °C in the BR2 reactor in Mol up to an accumulated dose of about 0.5 dpa.
UR - http://www.scopus.com/inward/record.url?scp=0035270883&partnerID=8YFLogxK
U2 - 10.13182/fst01-a11963297
DO - 10.13182/fst01-a11963297
M3 - Article
AN - SCOPUS:0035270883
SN - 0748-1896
VL - 39
SP - 569
EP - 573
JO - Fusion Technology
JF - Fusion Technology
IS - 2
ER -