Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX
Journal Article
·
· Journal of Nuclear Materials
- Oak Ridge Institute for Science and Education (ORISE), Oak Ridge, TN (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Princeton University, NJ (United States)
Here, we report the dependence of the lower divertor surface heat flux profiles, measured from infrared thermography and mapped magnetically to the mid-plane on loss power into the scrape-off layer (PLOSS), plasma current (Ip), and magnetic flux expansion (fexp), as well as initial results with lithium wall conditioning in NSTX. Here we extend previous studies to higher triangularity ~0.7 and higher Ip ≤ 1.2 MA. First we note that the mid-plane heat flux width mapped to the mid-plane, $$λ^{mid}_q$$, is largely independent of PLOSS for PLOSS ≥ 4 MW. $$λ^{mid}_q$$ is also found to be relatively independent of fexp; peak heat flux is strongly reduced as fexp is increased, as expected. Finally, $$λ^{mid}_q$$ is shown to strongly contract with increasing Ip such that $$λ^{mid}_q$$ ∝ I$$^{-1.6}_p$$ with a peak divertor heat flux of qdiv, peak ~ 15 MW/m2 when Ip = 1.2 MA and PLOSS ~ 6 MW. These relationships are then used to predict the divertor heat flux for the planned NSTX-Upgrade, with heating power between 10 and 15 MW, Bt = 1.0 T and Ip = 2.0 MA for 5 s.
- Research Organization:
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- Grant/Contract Number:
- AC02-09CH11466; AC05-00OR22725; AC05-06OR23100; AC52-07NA27344
- OSTI ID:
- 1898294
- Alternate ID(s):
- OSTI ID: 21579081
- Report Number(s):
- LLNL-JRNL-434147; 402075
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1 Vol. 415; ISSN 0022-3115
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U
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journal | November 2016 |
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