Flat-top cylinder indenter for mechanical characterization (FIMEC) is an indentation technique employing cylindrical punches with diameters ranging from 0.5 to 2 mm. The test gives pressure-penetration curves from which the yield stress can be determined. The FIMEC apparatus was developed to test materials in the temperature range from -180 to +200 degrees C. Recently, the heating system of FIMEC apparatus has been modified to operate up to 500 degrees C. So, in addition to providing yield stress over a more extended temperature range, it is possible to perform stress-relaxation tests at temperatures of great interest for several nuclear fusion reactor (NFR) alloys. Data on MANET-II, F82H mod., Eurofer-97, EM-10, AISI 316 L, Ti6Al4V and CuCrZr are presented and compared with those obtained by mechanical tests with standard methods. (c) 2007 Elsevier B.V. All rights reserved.

Montanari, R., Filacchioni, G., Iacovone, B., Plini, P., Riccardi, B. (2007). High temperature indentation tests on fusion reactor candidate materials. In Journal of Nuclear Materials (pp.648-652). AMSTERDAM : ELSEVIER SCIENCE BV [10.1016/j.jnucmat.2007.03.099].

High temperature indentation tests on fusion reactor candidate materials

MONTANARI, ROBERTO;IACOVONE, BENEDETTO;
2007-01-01

Abstract

Flat-top cylinder indenter for mechanical characterization (FIMEC) is an indentation technique employing cylindrical punches with diameters ranging from 0.5 to 2 mm. The test gives pressure-penetration curves from which the yield stress can be determined. The FIMEC apparatus was developed to test materials in the temperature range from -180 to +200 degrees C. Recently, the heating system of FIMEC apparatus has been modified to operate up to 500 degrees C. So, in addition to providing yield stress over a more extended temperature range, it is possible to perform stress-relaxation tests at temperatures of great interest for several nuclear fusion reactor (NFR) alloys. Data on MANET-II, F82H mod., Eurofer-97, EM-10, AISI 316 L, Ti6Al4V and CuCrZr are presented and compared with those obtained by mechanical tests with standard methods. (c) 2007 Elsevier B.V. All rights reserved.
12th International Conference on Fusion Reactor Materials (ICFRM-12)
Santa Barbara, CA
DEC 07-12, 2005
Rilevanza internazionale
contributo
2007
Settore ING-IND/21 - METALLURGIA
English
MECHANICAL CHARACTERIZATION; WELDED-JOINTS; FLAT
Intervento a convegno
Montanari, R., Filacchioni, G., Iacovone, B., Plini, P., Riccardi, B. (2007). High temperature indentation tests on fusion reactor candidate materials. In Journal of Nuclear Materials (pp.648-652). AMSTERDAM : ELSEVIER SCIENCE BV [10.1016/j.jnucmat.2007.03.099].
Montanari, R; Filacchioni, G; Iacovone, B; Plini, P; Riccardi, B
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/2108/47314
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