Improved CuCrZr/316L transition for plasma facing components
Different welding strategies were investigated to improve the tubular transition of CuCrZr to 316L in cooling pipes for actively cooled plasma facing components. Electron beam welding experiments have been carried out on tubular samples using different filler and adapter materials. After non-destruc...
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Veröffentlicht in: | Fusion engineering and design 2007-10, Vol.82 (15), p.1793-1798 |
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creator | Tabernig, Bernhard Rainer, Florian Scheiber, Karl-Heinz Schedler, Bertram |
description | Different welding strategies were investigated to improve the tubular transition of CuCrZr to 316L in cooling pipes for actively cooled plasma facing components. Electron beam welding experiments have been carried out on tubular samples using different filler and adapter materials. After non-destructive testing by dye penetrant and He-leak tight testing samples were tensile tested at RT and 400
°C to down-select promising candidates. Furthermore samples were taken for a metallographic examination in order to determine the integrity of the welds, the depth of penetration and the hardness profile across the weld. In the scanning electron microscope the weld microstructure and the formation of phases were studied. Good results were obtained by the use of a Ni-filler, an Inconel and explosive welded adapter. The tested samples of these variations fulfilled the strength requirements according to the ITER specification and showed an improved transition compared with the current solution of a pure Ni-adapter. The final down-selection will be based on the results of fatigue and torsion testing. |
doi_str_mv | 10.1016/j.fusengdes.2007.04.015 |
format | Article |
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°C to down-select promising candidates. Furthermore samples were taken for a metallographic examination in order to determine the integrity of the welds, the depth of penetration and the hardness profile across the weld. In the scanning electron microscope the weld microstructure and the formation of phases were studied. Good results were obtained by the use of a Ni-filler, an Inconel and explosive welded adapter. The tested samples of these variations fulfilled the strength requirements according to the ITER specification and showed an improved transition compared with the current solution of a pure Ni-adapter. The final down-selection will be based on the results of fatigue and torsion testing.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2007.04.015</identifier><identifier>CODEN: FEDEEE</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; CuCrZr ; EB welding ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Installations for energy generation and conversion: thermal and electrical energy ; ITER ; Nuclear fusion ; Plasma facing component</subject><ispartof>Fusion engineering and design, 2007-10, Vol.82 (15), p.1793-1798</ispartof><rights>2007 Elsevier B.V.</rights><rights>2007 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c407t-ad109ba2c682a5ab7fd9c4be6e17ace5b085c9e940e439f11e7123c5437c79f93</citedby></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.fusengdes.2007.04.015$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,780,784,789,790,3550,23930,23931,25140,27924,27925,45995</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=19372724$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Tabernig, Bernhard</creatorcontrib><creatorcontrib>Rainer, Florian</creatorcontrib><creatorcontrib>Scheiber, Karl-Heinz</creatorcontrib><creatorcontrib>Schedler, Bertram</creatorcontrib><title>Improved CuCrZr/316L transition for plasma facing components</title><title>Fusion engineering and design</title><description>Different welding strategies were investigated to improve the tubular transition of CuCrZr to 316L in cooling pipes for actively cooled plasma facing components. Electron beam welding experiments have been carried out on tubular samples using different filler and adapter materials. After non-destructive testing by dye penetrant and He-leak tight testing samples were tensile tested at RT and 400
°C to down-select promising candidates. Furthermore samples were taken for a metallographic examination in order to determine the integrity of the welds, the depth of penetration and the hardness profile across the weld. In the scanning electron microscope the weld microstructure and the formation of phases were studied. Good results were obtained by the use of a Ni-filler, an Inconel and explosive welded adapter. The tested samples of these variations fulfilled the strength requirements according to the ITER specification and showed an improved transition compared with the current solution of a pure Ni-adapter. The final down-selection will be based on the results of fatigue and torsion testing.</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>CuCrZr</subject><subject>EB welding</subject><subject>Energy</subject><subject>Energy. 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°C to down-select promising candidates. Furthermore samples were taken for a metallographic examination in order to determine the integrity of the welds, the depth of penetration and the hardness profile across the weld. In the scanning electron microscope the weld microstructure and the formation of phases were studied. Good results were obtained by the use of a Ni-filler, an Inconel and explosive welded adapter. The tested samples of these variations fulfilled the strength requirements according to the ITER specification and showed an improved transition compared with the current solution of a pure Ni-adapter. The final down-selection will be based on the results of fatigue and torsion testing.</abstract><cop>Amsterdam</cop><cop>New York, NY</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2007.04.015</doi><tpages>6</tpages></addata></record> |
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source | Elsevier ScienceDirect Journals Complete |
subjects | Applied sciences Controled nuclear fusion plants CuCrZr EB welding Energy Energy. Thermal use of fuels Exact sciences and technology Installations for energy generation and conversion: thermal and electrical energy ITER Nuclear fusion Plasma facing component |
title | Improved CuCrZr/316L transition for plasma facing components |
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