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Title:
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Irradiation testing of 316L(N)-IG austenitic stainless steel for ITER
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Author(s):
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Published by:
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Publication date:
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ECN
NUCLEAIR
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1998
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ECN report number:
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Document type:
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ECN-RX--98-002
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Article (scientific)
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Number of pages:
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24
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Published in: Paper submitted to ICFRM-8, 26-31 October 1997, Sendai, Japan (), , , Vol., p.-.
Abstract:
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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