Published April 2009 | Version v1
Journal article

Hydrogenic retention with high-Z plasma facing surfaces in Alcator C-Mod

  • 1. Massachusetts Institute of Technology Plasma Science and Fusion Center, 175 Albany St, Cambridge, MA 02139 (United States)
  • 2. FOM-Institute for Plasma Physics Rijnhuizen, Association Euratom-FOM, A member of the Trilateral Euregio Cluster, Postbus 1207, 3430 BE, Nieuwegein (Netherlands)

Description

The retention of deuterium (D) fuel in the Alcator C-Mod tokamak is studied using a new 'static' gas balance method. C-Mod solely employs high-Z molybdenum (Mo) and tungsten (W) for its plasma facing materials, with intermittent application of thin boron (B) films. The primarily Mo surfaces are found to retain large fractions, ∼20-50%, of the D2 gas fuelled per quiescent discharge, regardless of whether the Mo surfaces are cleaned of, or partially covered by, B films. Several experiments and calculations show that it is improbable that B retains significant fractions of the fuel. Rather, retention occurs in Mo and W surfaces through ion bombardment, implantation and diffusion to trap sites. Roughly 1% D of the incident ion fluence, ΦD, to surfaces is retained, and with no indication of the retention rate decreasing after 25 s of integrated plasma exposure. The magnitude of retention is significantly larger than that extrapolated from the results of laboratory studies for either Mo or W. The high levels of D/Mo in the near surface, measured directly post-campaign (∼0.01) in tiles and inferred from gas balance, are consistent with trapping sites for fuel retention in the Mo being created, or expanded, by high D atom densities in the near surface which arise as a result of high incident ion fluxes. Differences between C-Mod and laboratory retention results may be due to such factors as the multiply ionized B ions incident on the surface directly creating traps, the condition of Mo (impurities, annealing) and the high-flux densities in the C-Mod divertor which are similar to ITER, but 10-100x those used in laboratory studies. Disruptions produce rapid heating of the surfaces, releasing trapped hydrogenic species into the vessel for recovery. The measurements of the large amount of gas released in disruptions are consistent with the analysis of tiles removed from the vessel post-campaign-the campaign-integrated retention is very low, of order 1000x less than that observed in a single, non-disruptive discharge.

Availability note (English)

Available from http://dx.doi.org/10.1088/0029-5515/49/4/045009

Additional details

Identifiers

DOI
10.1088/0029-5515/49/4/045009;
PII
S0029-5515(09)91663-5;

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
49
Journal Issue
4
Journal Page Range
[18 p.]
ISSN
0029-5515
CODEN
NUFUAU

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41016737
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
ALCATOR DEVICE; BORON IONS; DIFFUSION; FIRST WALL; GAS FUELS; HYDROGEN; ITER TOKAMAK; MOLYBDENUM; RETENTION; SURFACES; TUNGSTEN
Descriptors DEC
CHARGED PARTICLES; CLOSED PLASMA DEVICES; ELEMENTS; FUELS; IONS; METALS; NONMETALS; REFRACTORY METALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS