Investigation of some cleaning surface treatments for the fabrication of ITER first wall panels by HIP
Creators
- 1. CEA Grenoble (DRT/LITEN/DTH), 38 (France)
- 2. CEA Grenoble (LITEN/DTH/LCPEM), 38 (France)
- 3. 2EFDA, Garching (Germany)
Description
Full text of publication follows: ITER First Wall (FW) panels are the innermost part of the ITER reactor. Metallic materials used for their manufacture are 316L(N)-IG stainless steel, a copper alloy and beryllium. Stainless steel material is a support structure for the copper alloy that serves as a heat sink material and also for the beryllium tiles that are a protective armour against the plasma. All these materials are bonded together by Hot Isostatic Pressing (HIP). Thus, several types of joints (Cu/Cu, Cu/SS, SS/SS or Cu/Be) are present in a FW panels. Their manufacturing requires a very strict and advanced metallic surface preparation in order to eliminate most of the organic or oxide layers that could prevent the diffusion process between the facing materials. In this field, our laboratory practice enables to obtain sufficiently clean metallic surfaces and high strength joints are obtained when small mockups are made. However, the manufacture of a large number of FW panels in the future requires to find a new cleaning process that is industrially relevant without a strong reduction of the joint's mechanical properties. In this paper we present our investigations to find an industrial solution to clean efficiently copper alloy and stainless steel materials in order to manufacture high strength Cu/Cu, SS/SS or Cu/SS joints. Products investigated are mainly acid liquids proposed by chemical Company and a more advanced technique that uses a plasma process. HIP joints are tested mechanically by making impact toughness and tensile measurements. Results obtained with these solutions are compared to those obtained in our Laboratory by using our own cleaning route. Moreover, XPS analyses are performed on small specimens that have been submitted to the same cleaning treatments in order to better understand the mechanical results of our specimens. (authors)
Availability note (English)
Available in abstract form only, full text entered in this recordAdditional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- INIS-FR--09-0888
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
- 40073735
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BERYLLIUM; CLEANING; COPPER ALLOYS; FIRST WALL; HOT PRESSING; ITER TOKAMAK; JOINTS; MECHANICAL PROPERTIES; OXIDES; PLASMA; SOLUTIONS; STAINLESS STEELS; THERMONUCLEAR REACTOR MATERIALS; X-RAY PHOTOELECTRON SPECTROSCOPY
- Descriptors DEC
- ALKALINE EARTH METALS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CLOSED PLASMA DEVICES; DISPERSIONS; ELECTRON SPECTROSCOPY; ELEMENTS; FABRICATION; HIGH ALLOY STEELS; HOMOGENEOUS MIXTURES; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATERIALS WORKING; METALS; MIXTURES; OXYGEN COMPOUNDS; PHOTOELECTRON SPECTROSCOPY; PRESSING; SPECTROSCOPY; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS