Tensile fracture behavior of high dose irradiated reduced activation ferritic/martensitic steel F82H

＊Hiroyasu Tanigawa

Presentation information

Oral Presentation

V. Fusion Energy Engineering » 501-2. Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[3L09-15] Material Engineering for Fusion Reactor (Low Activation Structural Material)

Mon. Mar 28, 2016 2:45 PM - 4:30 PM Room L (Lecture Rooms C C105)

Chair: Takeo Nishitani (NIFS)

3:45 PM - 4:00 PM

[3L13] Tensile fracture behavior of high dose irradiated reduced activation ferritic/martensitic steel F82H

＊Hiroyasu Tanigawa¹, Hideo Sakasegawa¹, Takanori Hirose¹, Yutai Katoh² (1.Japan Atomic Energy Agency, 2.Oak Ridge National Laboratory)

Keywords:Reduced activation ferritic/martensitic steel, high dose irradiation, tensile test

Reduced activation ferritic/martensitic steel, F82H, is the first candidate DEMO blanket structural material, and the preparation of high dose irradiation database is underway. 87 dpa irradiation was completed and post irradiation tensile tests were conducted at the irradiation temperature. The results of the tensile test and fractography on 300 degrees C irradiated specimens will be reported.