Published October 2007 | Version v1
Journal article

Optimization of the JET beryllium tile profile for power handling

  • 1. Associacao EURATOM-IST Centro de Fusao Nuclear, Instituto Superior Tecnico, 1049-001 Lisbon (Portugal)
  • 2. EURATOM/UKAEA Fusion Association, Abingdon OX14 3DB (United Kingdom)

Description

The primary objective of the JET ITER-like wall project is to install a beryllium main wall and a tungsten divertor. For beryllium, melting and thermal stress limit the maximum power density which can be tolerated in operation. The tile design has to allow routine plasma operation for ITER relevant scenarios, i.e., q95f ∼ [2.3-10] with high power input (Pin ≤ 30 MW) for pulse lengths of ∼10 s. This paper focuses on the power handling studies of the beryllium tiles for the outer poloidal limiters and ICRH horizontal protections, and the optimization of their design to achieve the operational goal described above

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2007.04.047

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2007.04.047;
PII
S0920-3796(07)00202-5;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
82
Journal Issue
15-24
Journal Page Range
p. 1846-1853
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
24. symposium on fusion technology
Acronym
SOFT-24
Dates
11-15 Sep 2006
Place
Warsaw (Poland)

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.