作者: Stuart Andrew Maloy , Michael Richard James , Walter Sommer jr , Gordon Jesse Willcutt jr , Manuel Lopez
DOI: 10.2320/MATERTRANS.43.633
关键词: Neutron 、 Irradiation 、 Corrosion 、 Radiochemistry 、 Rod 、 Materials science 、 Alloy 、 Composite material 、 Indentation hardness 、 Particle accelerator 、 Tungsten
摘要: For the Accelerator Production of Tritium (APT) and Driven Transmutation Facility (ADTF), tungsten is being proposed as a target material to produce neutrons. Previous work has shown that mechanical properties are degraded from irradiation in fission neutron flux but little been performed on high energy proton beam. In this study, rods were irradiated at 800 MeV Los Alamos Neutron Science Center (LANSCE) accelerator for six months. To avoid corrosion during irradiation, slip fit with thin (0.25 mm thick) 304L stainless steel (SS) or (0.125 annealed Alloy 718 tubing. After maximum dose 23.3 dpa Tirr = 50‐270 ◦ C, clad opened hot cells was removed. The then sliced into short compression specimens (∼ 3 long). Hardness tests assess effect their properties. Results show an increase hardness temperature yield stress dose.