[2O10-16] Fusion Reactor Materials (Reduced Activation Ferritic Steel, Beryllium Neutron Multiplier)

[2O12] Analysis on inhomogeneous deformation of neutron-irradiated dissimilar-metals joint for fusion reactors

*Takuya Nagasaka^1,2, Haiying Fu³, Masanori Yamazaki⁴, Takeshi Toyama⁴, Wenhai Guan⁵, Shuhei Nogami⁵, Hisashi Serizawa⁶, Hiroyasu Tanigawa⁷ (1. National Institute for Fusion Science, 2. The Graduate University for Advanced Studies, 3. Southwestern Institute of Physics, 4. Institute for Materials Research, Tohoku University, 5. Graduate School of Engineering, Tohoku University, 6. Joining and Welding Research Institute, Osaka University, 7. National Institutes for Quantum and Radiological Science and Technology)

Keywords:Fusion reactor blanket, Electron beam welding, Impact test

A dissimilar-metals weld joint between F82H steel and 316L steel was neutron-irradiated in BR-2 reactor, Belgium. The irradiated joint exhibited good ductility in post-irradiation impact tests. In order to estimate bonding strength, inhomogeneous deformation of the joint was analyzed with finite element method calculation and measurement on specimen shape after the impact tests.