Multiple Analytical Approach to Isotopic Transport Analysis in Magnetic Fusion Devices

Jonah D. Duran, Ezekial A. Unterberg, Mike P. Zach, William R. Wampler, Dmitry L. Rudakov, David C. Donovan

Research output: Contribution to journalArticlepeer-review

8 Scopus citations

Abstract

High-Z impurities released from plasma-material interactions have been shown to limit the performance of fusion plasmas, and understanding these impurity transport mechanisms throughout the plasma scrape-off layer is a major challenge. Presented herein is a study of tungsten (W) erosion and transport by uniquely measuring absolute quantities of isotopic W in order to determine the source of natural and enriched 182W isotopes that have traveled throughout the tokamak discharges on the DIII-D National Fusion Facility at General Atomics. Two primary analysis methods have been implemented to characterize this W on graphite collector probes that were inserted into DIII-D’s outboard midplane. Results from experiments using Rutherford backscattering spectrometry (RBS) have measured W particle areal densities down the centerline of the probes as high as 6E14 atoms/cm2 with a detection limit of 1E12 atoms/cm2. Laser ablation inductively coupled plasma mass spectrometry (LAMS) has confirmed the elemental trends found with RBS and has provided additional insight into collector probe surface profiles. Two-dimensional elemental and isotopic maps from LAMS are used to reveal new collector probe features and further refine the source of collected W. Variations in isotopic profiles and total W content are coupled to (a) the face of the probe being analyzed, (b) the dimensions of the probe, and (c) the plasma pulse parameters that were used during probe exposure. These results provide one-of-a-kind empirical evidence that is now being utilized for validation of tokamak impurity transport through theoretical models and in codes such as 3D-LIM and OEDGE.

Original languageEnglish
Pages (from-to)493-498
Number of pages6
JournalFusion Science and Technology
Volume75
Issue number6
DOIs
StatePublished - Aug 18 2019

Funding

The authors would like to recognize support by the U.S. Department of Energy (DOE) under DE-SC0016318 (University of Tennessee, Knoxville), DE-AC05-00OR22725 (Oak Ridge National Laboratory), and DE-SC0014664 (Oak Ridge Associated Universities). This material is also based upon work supported by the DOE Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under award DE-FC02-04ER54698. Additional recognition is given to Sandia National Laboratories, which is a multimission laboratory managed and operated by National Technology & Engineering Solutions of Sandia, LLC, a wholly owned subsidiary of Honeywell International Inc., for the DOE National Nuclear Security Administration under contract DE-NA0003525. This manuscript has been authored in part by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the DOE. The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

Keywords

  • DIII-D
  • Tungsten
  • isotopes
  • plasma-material interactions
  • tokamak

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