Abstract
A new helium (He) loop was used to study the helium-cooled modular divertor with multiple jets (HEMJ) at incident heat fluxes q″ ≤ 6.6 MW/m2 as part of the joint US-Japan effort on plasma-facing components evaluation by tritium plasma, heat, and neutron irradiation experiments (PHENIX). These studies were performed at prototypical pressures of 10 MPa and inlet temperatures ranging from 30 °C to 300 °C. The effect of varying the distance between the inner jets cartridge and the outer shell from 0.44 to 0.9 mm was also investigated.The Nusselt number results for two different tungsten-alloy test sections were in good agreement for q″ = 1.5–6.6 MW/m2. The experiments also suggest that the loss coefficient KL is essentially constant. These and KL results were used to estimate the maximum heat flux that can be accommodated by the divertor under prototypical conditions and the coolant pumping power as a fraction of the incident thermal power β. The agreement over the broad range of experimental parameters studied suggests that these results at near-prototypical conditions can be extrapolated with reasonable confidence to the operating conditions expected for the HEMJ design.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.