Title of article :
Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion)
Author/Authors :
Mota، نويسنده , , F. and Vila، نويسنده , , R. and Ortiz، نويسنده , , C. and Garcia، نويسنده , , A. and Casal، نويسنده , , N. and Ibarra، نويسنده , , A. and Rapisarda، نويسنده , , D. and Queral، نويسنده , , V.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2011
Abstract :
Present pathway to fusion reactors includes a rigorous material testing program. To reach this objective, irradiation facilities must produce the displacement damage per atom (dpa), primary knock-on atom (PKA) spectrum and gaseous elements by transmutation reactions (He, H) as closely as possible to the ones expected in the future fusion reactors (as DEMO).The irradiation parameters (PKA spectra and damage function) of some candidate materials for fusion reactors (Al2O3, SiC and Fe) have been studied and then, the suitability of some proposed experimental facilities, such as IFMIF and TechnoFusion, to perform relevant tests with these materials has been assessed.The following method has been applied: neutron fluxes present in different irradiation modules of IFMIF have been calculated by the neutron transport McDeLicious code. In parallel, the energy differential cross sections of PKA have been calculated by using the NJOY code. After that, the damage generated by the PKA spectra was analyzed using the MARLOWE code (binary collision approximation) and custom analysis codes. Finally, to analyze the ions effects in different irradiation conditions in the TechnoFusion irradiation area, the SRIM and Marlowe codes have been used. The results have been compared with the expected ones for a DEMO HCLL reactor.
Keywords :
Al2O3 , SiC , IFMIF , TechnoFusion , Irradiation damage , Demo
Journal title :
Fusion Engineering and Design
Journal title :
Fusion Engineering and Design