Testing of high heat flux components manufactured by ENEA for ITER divertor
Creators
- 1. Associazione EURATOM-ENEA sulla Fusione, C.R. Frascati, Via E. Fermi, 45, IT-00044 Frascati (Italy)
- 2. Association Euratom CEA, CEA/DSM/IRFM, Cadarache, 13108 Saint-Paul-lez-Durance (France)
- 3. ITER Organisation, Cadarache Centre, Bat 519, F-13108 Saint Paul lez Durance (France)
Description
ENEA is involved in the International Thermonuclear Experimental Reactor (ITER) R and D activities and in particular in the manufacturing of high heat flux plasma-facing components, such as the divertor targets. During the last years ENEA has manufactured actively cooled mock-ups by using different technologies, namely brazing, diffusion bonding and HIPping. A new manufacturing process that combines two main techniques PBC (Pre-Brazed Casting) and the HRP (Hot Radial Pressing) has been set up and widely tested. A full monoblock medium scale vertical target, having a straight CFC armoured part and a curved W armoured part, was manufactured using this process. The ultrasonic method was used for the non-destructive examinations performed during the manufacturing of the component, from the monoblock preparation up to the final mock-up assembling. The component was also examined by thermography on SATIR facility (CEA, France), afterwards it was thermal fatigue tested at FE200 (200 kW electron beam facility, CEA/AREVA France). The successful results of the thermal fatigue testing performed according the ITER requirements (10 MW/m2, 3000 cycles of 10 s on both CFC and W part, then 20/15 MW/m2, 2000 cycles of 10 s on CFC/W part, respectively) have confirmed that the developed process can be considerate a candidate for the manufacturing of monoblock divertor components. Furthermore, a 35-MW/m2 Critical Heat Flux was measured at relevant thermal-hydraulics conditions at the end of the testing campaign. This paper reports the manufacturing route, the thermal fatigue testing results, the pre and post non-destructive examination and the destructive examination performed on the ITER vertical target medium scale mock-up. These activities were performed in the frame of EFDA contracts (04-1218 with CEA, 93-851 JN with AREVA and 03-1054 with ENEA).
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2008.12.087Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2008.12.087;
- PII
- S0920-3796(08)00545-0;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 84
- Journal Issue
- 2-6
- Journal Page Range
- p. 309-313
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 25. symposium on fusion technology
- Acronym
- SOFT-25
- Dates
- 15-19 Sep 2008
- Place
- Rostock (Germany)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41031128
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICAL HEAT FLUX; DIVERTORS; ITER TOKAMAK; MANUFACTURING; NEA; THERMAL FATIGUE
- Descriptors DEC
- CLOSED PLASMA DEVICES; FATIGUE; HEAT FLUX; INTERNATIONAL ORGANIZATIONS; MECHANICAL PROPERTIES; OECD; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.