Published April 2005
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Irradiation of Steel in PbBi
Description
T91 ferritic-martensitic steel is a candidate material for the structures and fuel cladding of future ADS reactors. Its behaviour under the combined effects of irradiation and contact with ADS coolant has still to be assessed, in particular the corrosion behaviour. In the frame of IP-EUROTRANS / DEMETRA project, SCK-CEN proposed to irradiate metallurgical samples under PbBi. Additional samples under water or inert gas allow to discriminate the effect of the irradiation from the effect of PbBi. The programme is called ASTIR (Ads Steel T91 IRradiation).Two different irradiations are to be performed at 300 degrees Celsius and 450 degrees Celsius , up to a fluence of 2 and 5 dpa
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Additional details
Identifiers
Publishing Information
- Publisher
- Belgian Nuclear Research Center SCK-CEN
- Imprint Place
- Mol (Belgium)
- Imprint Title
- Scientific Report 2004
- Imprint Pagination
- 186 p.
- Journal Page Range
- p. 93-94
- Report number
- INIS-BE--0009
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 36097560
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- BELGIUM; BISMUTH; BR-2 REACTOR; CLADDING; CORROSION; IRRADIATION; IRRADIATION PLANTS; LEAD; MARTENSITIC STEELS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; PROGRESS REPORT; REACTOR INSTRUMENTATION; SPENT FUELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; DEPOSITION; DEVELOPED COUNTRIES; DOCUMENT TYPES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EUROPE; FUELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING; MATERIALS TESTING REACTORS; METALS; NUCLEAR FACILITIES; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; STEELS; SURFACE COATING; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- The abstract is a contribution to the 2004 Scientific Report of the Belgian Nuclear Research Centre SCK-CEN