Published 2004 | Version v1
Miscellaneous Open

Results and analysis of high heat flux tests on a full scale vertical target prototype of ITER divertor

  • 1. Association Euratom-CEA, Centre d'Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. de Recherches sur la Fusion Controlee
  • 2. EFDA Close Support Unit, Garching (Germany)
  • 3. Framatome, 71 - Le Creusot (France)

Description

After an extensive development program, a Full-Scale Divertor Target prototype (VTFS) manufactured with all the main features of the corresponding ITER divertor, was intensively tested in the high heat flux FE200 facility. The prototype consists of four units having a full mono-block geometry. The lower part (CFC armour) and the upper part (W armour) of each mono-block were joined to the solution annealed, quenched and cold worked CuCrZr tube by HIP technique. The CFC mono-block was successfully tested up to 1000 cycles at 23 MW/m2 without any indication of failure. This value is well beyond the ITER design target of 300 cycles at 20 MW/m2. The W mono-block endured ∼600 cycles at 10 MW/m2. This value of flux is one order of magnitude higher than the ITER design target for the upper part of the vertical target. Fatigue damage is observed when pursuing the cycling up to 15 MW/m2. A first stress analysis seems to predict these factual results. However, macro-graphic examinations should bring a better damage valuation. Meanwhile, the fatigue testing will continue on the W healthy part of the VTFS prototype with castellation located on the heated surface (reducing the stresses close to the W-Cu interface). (authors)

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
14 p.
Report number
INIS-FR--3568

Conference

Title
23. Symposium on Fusion Technology
Dates
20-24 Sep 2004
Place
Venice (Italy)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
36069451
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIVERTORS; FEASIBILITY STUDIES; ITER TOKAMAK; MECHANICAL TESTS; MOCKUP; OPTIMIZATION; SCALE MODELS; THERMAL CYCLING
Descriptors DEC
CLOSED PLASMA DEVICES; MATERIALS TESTING; STRUCTURAL MODELS; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
4 refs.