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ECN publicatie:
Irradiation testing of 316L(N)-IG austenitic stainless steel for ITER
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ECN publicatienummer: Publicatie type:
ECN-RX--98-002 Artikel wetenschap tijdschrift
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Gepubliceerd in: Paper submitted to ICFRM-8, 26-31 October 1997, Sendai, Japan (), , , Vol., p.-.

Within the framework of the European Fusion Technology Programme and theRandD for International Thermonuclear Experimental Reactor (ITER), ECN is investigating the irradiation behaviour of the structural materials for ITER. The main structural material for ITER is austenitic stainless steel Type 316L(N)-ICI. The operating temperatures of (parts of) the components are envisaged to range between 350 and 700K. A significant part of the dose-temperature domain of irradiation conditions relevant for ITER has already been explored. There is, however, very little data at about 600K. Available data tend to indicate a maximum in the degradation of the mechanical properties after irradiation at this temperature, e.g. a minimum in ductility and a maximum of hardening. Therefore an irradiation program for plate material 316L(N)-IG, its Electron Beam (EB) weldments and Tungsten Inert Gas (TIG) weld metal, and also including Hot Isostatically Pressed (HIP) 316L(N) powder and solid-solid joints, was set up in 1995. Irradiations have been carried out in the High Flux Reactor (HFR) in Petten at a temperature of 600K, at dose levels from 1 to 10 dpa. The paper presents the currently available post-irradiation test results. Next to tensile and fracture toughness data on plate, EB and TIG welds, first results of powder HIP-ed material are included. 15 refs.

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