Evaporated lithium surface coatings in NSTX

Kugel, Henry W.; Mansfield, Dennis K.; Maingi, Rajesh; Bell, Michael G.; Bell, Ronald E.; Allain, Jean Paul; Gates, David A.; Gerhardt, Stephan P.; Kaita, Robert; Kallman, Joshua B.; Kaye, Stanley M.; LeBlanc, Benoit P.; Majeski, Richard P.; Menard, Jonathan E.; Mueller, Dennis S.; Ono, Masayuki; Paul, Stephen F.; Raman, Roger; Roquemore, Alvin L.; Ross, Patrick W.; Sabbagh, Steven Anthony; Schneider, Hans; Skinner, Charles H.; Soukhanovskii, V. A.; Stevenson, T. A.; Timberlake, John R.; Wampler, William R.; Wilgren, J.; Zakharov, Leonid E.

doi:10.1016/j.jnucmat.2009.01.262

Evaporated lithium surface coatings in NSTX

Journal Article · Tue Jan 27 00:00:00 EST 2009 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2009.01.262· OSTI ID:1898303

Kugel, Henry W. ^[1]; Mansfield, Dennis K. ^[1]; Maingi, Rajesh ^[2]; Bell, Michael G. ^[1]; Bell, Ronald E. ^[1]; Allain, Jean Paul ^[3]; Gates, David A. ^[1]; Gerhardt, Stephan P. ^[1]; Kaita, Robert ^[1]; Kallman, Joshua B. ^[1]; Kaye, Stanley M. ^[1]; LeBlanc, Benoit P. ^[1]; Majeski, Richard P. ^[1]; Menard, Jonathan E. ^[1]; Mueller, Dennis S. ^[1]; Ono, Masayuki ^[1]; Paul, Stephen F. ^[1]; Raman, Roger ^[4]; Roquemore, Alvin L. ^[1]; Ross, Patrick W. ^[1] more »

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Purdue Univ., West Lafayette, IN (United States)
Univ. of Washington, Seattle, WA (United States)
Columbia Univ., New York, NY (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Two lithium evaporators were used to evaporate more than 100 g of lithium on to the NSTX lower divertor region. Prior to each discharge, the evaporators were withdrawn behind shutters, where they also remained during the subsequent HeGDC applied for periods up to 9.5 min. After the HeGDC, the shutters were opened and the LITERs were reinserted to deposit lithium on the lower divertor target for 10 min, at rates of 10–70 mg/min, prior to the next discharge. Overall, the major improvements in plasma performance from these lithium depositions include: (1) plasma density reduction as a result of lithium deposition; (2) suppression of ELMs; (3) improvement of energy confinement in a low-triangularity shape; (4) improvement in plasma performance for standard, high-triangularity discharges; (5) reduction of the required HeGDC time between discharges; (6) increased pedestal electron and ion temperature; (7) reduced SOL plasma density; and (8) reduced edge neutral density.

View Accepted Manuscript (DOE)

Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Contributing Organization:: NSTX Team

Grant/Contract Number:: AC02-76CH03073; AC04-94AL85000; AC05-00OR22725; AC52-07NA27344; W-7405-ENG-48

OSTI ID:: 1898303

Alternate ID(s):: OSTI ID: 21346328

Report Number(s):: LLNL-JRNL-410677; 370103

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 390-391; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (14)

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