Irradiation of structural materials in contact with lead bismuth eutectic in the high flux reactor
In the framework of the materials domain DEMETRA in the European Transmutation research and development project EUROTRANS, irradiation experiment IBIS has been performed in the High Flux Reactor in Petten. The objective was to investigate the synergystic effects of irradiation and lead bismuth eutec...
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Veröffentlicht in: | Journal of nuclear materials 2011-08, Vol.415 (3), p.311-315 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | In the framework of the materials domain DEMETRA in the European Transmutation research and development project EUROTRANS, irradiation experiment IBIS has been performed in the High Flux Reactor in Petten. The objective was to investigate the synergystic effects of irradiation and lead bismuth eutectic exposure on the mechanical properties of structural materials and welds. In this experiment ferritic martensitic 9 Cr steel, austenitic 316L stainless steel and their welds have been irradiated for 250 Full Power Days up to a dose level of 2
dpa. Irradiation temperatures have been kept constant at 300
°C and 500
°C.
During the post-irradiation test phase, tensile tests performed on the specimens irradiated at 300
°C have shown that the irradiation hardening of ferritic martensitic 9 Cr steel at 1.3
dpa is 254
MPa, which is in line with the irradiation hardening obtained for ferritic martensitic Eurofer97 steel investigated in the fusion program. This result indicates that no LBE interaction at this irradiation temperature is present. A visual inspection is performed on the specimens irradiated in contact with LBE at 500
°C and have shown blackening on the surface of the specimens and remains of LBE that makes a special cleaning procedure necessary before post-irradiation mechanical testing. |
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ISSN: | 0022-3115 1873-4820 |
DOI: | 10.1016/j.jnucmat.2011.04.035 |