Published August 2015 | Version v1
Journal article

Review of the ITER diagnostics suite for erosion, deposition, dust and tritium measurements

  • 1. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)
  • 2. F4E, Torres Diagonal Litoral B3, Barcelona (Spain)
  • 3. Institut für Energieforschung – Plasmaphysik, Forschungszentrum Jülich GmbH, Association EURATOM – Forschungszentrum Jülich, D-52425 Jülich (Germany)

Description

Dust and tritium inventories in the vacuum vessel have upper limits in ITER that are set by nuclear safety requirements. Erosion, migration and re-deposition of wall material together with fuel co-deposition will be largely responsible for these inventories. The diagnostic suite required to monitor these processes, along with the set of the corresponding measurement requirements is currently under review given the recent decision by the ITER Organization to eliminate the first carbon/tungsten (C/W) divertor and begin operations with a full-W variant Pitts et al. [1]. This paper presents the result of this review as well as the status of the chosen diagnostics

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2015.01.039

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2015.01.039;
PII
S0022-3115(15)00052-5;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
463
Journal Page Range
p. 180-184
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
21. international conference on plasma-surface interactions in controlled fusion devices
Acronym
Plasma-Surface Interactions 21
Dates
26-30 May 2014
Place
Kanazawa (Japan)

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.