27th IEEE Symposium on Fusion Engineering

Session

M.OP2: Materials I

M.OP2

5 Jun 2017, 16:00

Marriott Shanghai City Center

530. Application of Materials Science Advances to Fusion Energy

Dr Steven J. Zinkle (University of Tennessee)

05/06/2017, 16:00

Materials and fabrication

Invited Oral

The development of practical fusion energy as a commercial energy source is widely acknowledged as one of the greatest scientific and technical challenges for the 21^st century. Due to the extreme operating conditions in the first wall and blanket regimes, utilization of very high performance materials is vital for achieving a viable cost-competitive fusion reactor design. The...

417. Thermomechanical properties of nanostructured W based coatings under ITER-relevant thermal loads

Mr Edoardo Besozzi (Politecnico di Milano)

05/06/2017, 16:20

Materials and fabrication

Oral

The full tungsten (W) divertor of ITER will suffer from extreme thermal loads during both steady and transient operating conditions. These thermal loads, together with energetic species bombardment from the plasma, induce W surface erosion, melting and recrystallization. The sputtered particles could migrate and form micrometric thick co/re-deposits on the peripheral regions of the divertor....

461. EFFECTS OF TEMPERATURE AND HE CONCENTRATION ON FORMATION AND GROWTH OF HE BUBBLE IN BCC IRON UNDER IRRADIATION

Jie Zhan (University of Science and Technology of China)

05/06/2017, 16:40

Materials and fabrication

Oral

Helium atoms, produced at high rates in steels in fusion environment, are inclined to be deeply trapped in small vacancy clusters and microstructural features due to its low solubility in metal. Eventually, the formation of He bubbles significantly degrades the mechanical properties of materials. Therefore, it is important to understand the nucleation of He bubbles in steels, both in the bulk...

323. Effects of high-energy C ions irradiation on the D retention behavior in V-5Cr-5Ti

Mr Yu-Ping Xu (Institute of Plasma Physics, Chinese Academy of Sciences)

05/06/2017, 17:00

Materials and fabrication

Oral

Alloys based upon the V-Cr-Ti system (e.g. V-4Cr-4Ti, V-5Cr-5Ti) are attractive candidate structural materials in future fusion reactors because of their low activation properties, high thermal stress factor, good strength at elevated temperatures, and usable fabrication properties. However, the high hydrogen isotope retention in vanadium alloys has been a serious concern in the potential...

451. The experimental investigation of wetting property for liquid lead lithium alloy with breeder blanket materials

Prof. Weihua Wang (Institute of Applied Physics, Army Officer Academy)

05/06/2017, 17:20

Blankets and tritium breeding

Oral

The dual-cooled lead lithium (PbLi) blanket is considered as one of the main options for the Chinese DEMO reactor. The liquid PbLi alloy is used as breeder material and coolant. The Reduced Activation Ferritic/Martensitic (RAFM) steel and the silicon carbide fiber (SiCf) are selected as its structural material and functional material respectively. In the present experimental investigation, the...

160. Design, synthesis and characterization of Li4SiO4-based solid solutions as advanced tritium breeders

Linjie Zhao (China Academy of Engineering Physics)

05/06/2017, 17:40

Blankets and tritium breeding

Oral

Linjie Zhao*, Xiaojun Chen, Chengjian Xiao, Yu Gong, Heyi Wang, Xinggui Long, Shunming Peng

Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621999, China

*Corresponding author : zhaolinjie1989@163.com

The breeding blanket is a key component of the fusion reactor since it involves tritium breeding and energy extraction, both of which are...