Reduced activation ferritic steel alloys such as F82H are the candidate materials for the first wall of DEMO reactors.For self-cooled breeding blankets,the first wall will be subjected to bi-direction
The transient thermal shock performances and relevant damage mechanism of pure W and lutecium doped W alloys were investigated via a repetitive laser beam heat load test to simulate the transient heat
W-3wt%Lu2O3 composites were prepared by mechanical milling and spark plasma sintering.The W-3wt%Lu2O3 composites were maintained in a vacuum at room temperature,and irradiated with a He+(He+ion beam f
Austenitic stainless steels 316L have been widely utilized for industrial application,especially,as the candidate structural materials for fusion reactor.It is well known that helium atoms can be trap
Beryllium is planned to be used as a neutron multiplier in the Helium-cooled ceramic breeder(HCCB)test blanket module(TBM)which is the primary option of the Chinese TBM program.The character of the mi
Tungsten-based materials form a prime candidate of plasma facing components in fusion power reactors,and are subject to substantial amount of radiation damage from the bombardments of fast neutrons,as
The source term caused by activated corrosion products(ACPs)is an important radiation hazard in water-cooled fusion reactor,which directly determines the occupational radiation exposure during operati
Fe-based alloys of bcc phase are considered as the promising structural materials in fusion reactor.Large amounts of H impurities are produced concurrently along with irradiation damage in the structu
Plasma disruption would induce large eddy current and generate huge electromagnetic force in the vacuum vessel and other in vessel components of the Tokamak fusion reactor.To evaluate the safety of To