Thermal analysis of titanium drive-in target for D-D neutron generation.
Thermal analysis was performed for a titanium drive-in target of a D-D neutron generator. Computational fluid dynamics code CFX-5 was used in this study. To define the heat flux term for the thermal analysis, beam current profile was measured. Temperature of the target was calculated at some of the operating conditions. The cooling performance of the target was evaluated by means of the comparison of the calculated maximum target temperature and the critical temperature of titanium.
Jung
N S
NS
Department of Nuclear Engineering, Seoul National University, Seoul, Republic of Korea. vandegra@plaza.snu.ac.kr
Kim
I J
IJ
Kim
S J
SJ
Choi
H D
HD
D003198:Computer Simulation; D008956:Models, Chemical; D009502:Neutrons; D011829:Radiation Dosage; D012542:Scattering, Radiation; D013696:Temperature; D014025:Titanium / Q000737:chemistry* / Q000528:radiation effects*
D014025:Titanium