FY 2016 Fusion Energy Sciences (FES) Theory and Simulation Performance Target

Technical Report · Sat Dec 31 00:00:00 EST 2016

DOI:https://doi.org/10.2172/1471207· OSTI ID:1471207

Chang, C. S. ^[1]; Churchill, R. M. ^[1]; Hager, R. ^[1]; Ku, S. ^[1]; Stotler, D. ^[1]; Xu, X. Q. ^[2]; Chen, Bin ^[2]; Cohen, B. ^[2]; Joseph, I. ^[2]; Rognlien, T. ^[2]; Tand, T. F. ^[2]; Umansky, Maxim ^[2]; Myra, J. ^[3]

---

1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
3. Lodestar Research Corp., Boulder, CO (United States)

Annual target: Predicting the magnitude and scaling of the divertor heat load width in magnetically confined burning plasmas is a high priority for the fusion program and ITER. One of the key unresolved physics issues is what sets the heat flux width at the entrance to the divertor region. Perform massively parallel simulations using 3D edge kinetic and fluid codes to determine the parameter dependence of the heat load width at the divertor entrance and compute the divertor plate heat flux applicable to moderate particle recycling conditions. Comparisons will be made with data from DIII-D, NSTX-U, and C-Mod.

• Research Organization: USDOE Office of Science (SC), Washington, D.C. (United States). Fusion Energy Sciences (FES)
• Sponsoring Organization: USDOE Office of Science (SC), Fusion Energy Sciences (FES)
• DOE Contract Number: AC02-09CH11466; FC02-99ER54512; FC02-04ER54698; FG02-97ER54392; AC05-00OR22725; AC02-05CH11231; AC52-07NA27344
• OSTI ID: 1471207
• Report Number(s): DOE-1471207; TRN: US1902859
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY