Effect of Test Blanket Module on Triton Burn-up in DIII-D Tokamak

Time resolved measurements of triton burnup on DIII-D tokamak have been performed using a newly restored and upgraded 14~MeV neutron emission monitor based on silicon surface barrier diode. Neutron and energetic ion relevant data have been analyzed for the dedicated ITER Test Blanket Module (TBM) mockup plasma experiments. During the TBM on period, no observable change was recorded by a Faraday type fast ion loss collector, but a decrease in D-D neutron yield was usually encountered with a drop in plasma density. With full current applied on TBM coils, coincident reduction in 14 MeV neutron counts was prominent, as well as the ratio of 14~MeV D-T neutrons to 2.45~MeV D-D neutrons. In some cases, these behaviors were accompanied by a slight increase in signal of ion cyclotron emission loops attached behind the plasma-facing graphite protection module. Deterioration in triton confinement was observed to be weaker with partial current applied to the TBM and did not occur at all for no TBM current.