Published 2007 | Version v1
Miscellaneous

Damage modelling in Plasma Facing Components

  • 1. Bordeaux-1 Univ. des Sciences et Technologies-3, LCTS, Lab. des Composites Thermostructuraux, CNRS-UMR 5801, 33 - Pessac, (France)
  • 2. Association Euratom-CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. de Recherches sur la Fusion Controlee

Description

Full text of publication follows: The plasma facing components (PFC) of controlled fusion devices are submitted to high heat fluxes in operating conditions (10 MW/m2 for Tore Supra and up to 20 MW/m2 for ITER, Cadarache, France). Active cooling is required to maintain a reasonable surface temperature and to avoid critical heat flux and melting of the components. The PFC developed for Tore Supra are made of a carbon/carbon (C/C) composite flat tile bonded to a copper alloy heat sink. Under operating conditions, because of the thermal expansion mismatch existing between the C/C composite and the copper alloy, these components withstand significant stresses which induce damage in the C/C material as well as at the copper/composite interface. Design tools are thus required in order to analyse the initiation and the propagation of damage in thermally loaded PFC. The present study describes a modelling approach aimed at predicting damage in actively cooled PFC. For this purpose, dedicated experimental procedures have been developed and sound constitutive laws taking into account the damage related non linear behaviour of both the C/C material and the Cu-C/C joint have been established. Various tests have first been performed on C/C samples in tension and compression, within the fibre axis and off-axis, as well as in shear using a Iosipescu type device, in order to carefully analyse the non-linear mechanical behaviour of this material. A constitutive law able to handle complex multiaxial loadings, established within a classical thermodynamical framework and using scalar damage variables, was then identified. Tensile and shear tests were also performed on C/C-Cu samples in order to identify a cohesive zone model representative of the damageable behaviour of the joint. These constitutive laws were then introduced in a numerical model representative of a PFC. Obtained results have evidenced the progressive development of damage which takes place in the assembly when submitted to fatigue heat loads. Such an approach can be used to optimise the design of the component. (authors)

Availability note (English)

Available in abstract form only, full text entered in this record

Additional details

Publishing Information

Imprint Pagination
1 p.
Report number
INIS-FR--09-0512

Conference

Title
13. International Conference on Fusion Reactor Materials
Acronym
ICFRM-13
Dates
10-14 Dec 2007
Place
Nice (France)

INIS

Country of Publication
France
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40067790
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CARBON; COPPER; COPPER ALLOYS; CRITICAL HEAT FLUX; DAMAGE; DESIGN; FIRST WALL; HEAT SINKS; ITER TOKAMAK; NONLINEAR PROBLEMS; SIMULATION; THERMAL EXPANSION; TORE SUPRA TOKAMAK
Descriptors DEC
ALLOYS; CLOSED PLASMA DEVICES; ELEMENTS; EXPANSION; HEAT FLUX; METALS; NONMETALS; SINKS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS