I. Bobin-Vastra
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Publication
Featured researches published by I. Bobin-Vastra.
Fusion Engineering and Design | 2002
W. Daenner; M Merola; P. Lorenzetto; A. Peacock; I. Bobin-Vastra; L Briottet; P Bucci; D Conchon; A. Erskine; F Escourbiac; M Febvre; M Grattarola; C.G Hjorth; G Hofmann; A Ilzhoefer; K Lill; A Lind; J. Linke; W Richards; E Rigal; M. Roedig; F Saint-Antonin; B Schedler; J Schlosser; S. Tähtinen; E. Visca
This paper summarises the European R&D efforts for the manufacture of shield modules and divertor cassettes for the International Thermonuclear Experimental Reactor (ITER), including their plasma facing components. The various development steps are described as they had to be taken to resolve the fabrication issues, and to keep track with the evolving design requirements and solutions. For all components, the manufacturing feasibility has been demonstrated on prototype scale which puts Europe in the position to start the procurement as soon as the decision about ITER construction is taken. The time period remaining until then is used to optimise the fabrication processes and to develop more cost effective alternatives.
Fusion Engineering and Design | 2000
M Merola; I. Bobin-Vastra; A Cardella; M Febvre; L Giancarli; L Plöchl; J.F Salavy; A Salito; B Schedler; G. Vieider
Abstract The European contribution to the development of the ITER baffle will culminate with the fabrication of a full scale prototype with a CFC–plasma spray armour. This paper describes the main features of the prototype as well as the extensive R&D carried out to ensure that the component is fabricated with the required quality.
symposium on fusion technology | 2003
C. Boudot; I. Bobin-Vastra; P. Lorenzetto; D Conchon; A. Cottin; J Jacquinot; D Cauvin; M Febvre
The aim of this paper is to present the results of a manufacturing program that was implemented to demonstrate the feasibility for manufacturing the primary first wall panels, including a part of R&D work concerning the joining of Beryllium plates onto a Glidcop heat sink by HIPing or brazing.
symposium on fusion technology | 2001
I. Bobin-Vastra; M Febvre; B Schedler; L Plöchl; Y Bouveret; D Cauvin; G Raisson; M Merola
Abstract The ITER divertor baffle is one of the Plasma facing components which are developed in the frame of the ITER concept. The supply consisted in the manufacturing of four panels with four First Wall geometries using macroblock or heat sink+armour concepts. DS-Copper, and CuCrZr were the materials for the heat sink, and CFC or Tungsten Plasma spray were the armour. The panels included two Copper-based tubes each. The final purpose is the comparison of the fabricability of each type and the performances of each panel under heat fluxes.
symposium on fusion technology | 2001
I. Bobin-Vastra; M Febvre; P. Lorenzetto; Y Bouveret; D Cauvin; G Raisson; D Conchon
In the frame of the Primary Wall Module prototype manufacturing for ITER, a consistent R&D phase was conducted in order to identify the industrial allowable tolerances and manufacturing problems which would occur when joining pieces by HIPping process during the PW module manufacturing. The purpose of this development was to give as industrial as possible manufacturing routes for joining together large Stainless Steel or DS-Copper pieces with Stainless Steel tubes and for bonding Beryllium tiles onto a curved component surface. The study concerned surface preparations, allowable gaps and joint geometry, Beryllium tile geometry, Titanium interlayer thickness, … This R&D phase also allowed the development and validation of different ultrasonic inspection tools needed for plate-plate, tube-plate, edge to edge plate bonding.
symposium on fusion technology | 2001
M Febvre; I. Bobin-Vastra; P. Lorenzetto; Y Bouveret; D Cauvin; G Raisson; D Conchon
Abstract In the frame of the Blanket development programme for ITER, the design envisaged a blanket-shield constructed from modules. Primary Wall Modules consisted of a water-cooled austenitic stainless steel (S.S.) Shield Block and a First Wall, as an integral part of it. The Primary First Wall uses a DS-copper alloy as the heat sink material bonded to the shield block and a protection material such as Beryllium, to cope with the plasma/wall interaction. The module was designed to sustain a peak heat flux of 0.5 MW/m2. A manufacturing program was implemented to demonstrate the feasibility for joining the Primary First Wall onto the Shield, which included the manufacture of small scale and medium scale mock-ups, before the manufacture of a prototype. The aim of the paper is to present the different steps and results of a Medium Scale Module manufacturing.
symposium on fusion technology | 2005
I. Bobin-Vastra; F. Escourbiac; M. Merola; P. Lorenzetto
Fusion Engineering and Design | 2013
G. Pintsuk; I. Bobin-Vastra; S. Constans; P. Gavila; M. Rödig; B. Riccardi
symposium on fusion technology | 2005
F. Escourbiac; I. Bobin-Vastra; V. Kuznetsov; M. Missirlian; Bertram Schedler; J. Schlosser
Fusion Engineering and Design | 2006
P. Lorenzetto; A. Peacock; I. Bobin-Vastra; L. Briottet; P. Bucci; G. Dell’Orco; K. Ioki; M. Roedig; P. Sherlock