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Extra resources for Basic Studies In The Field Of High Temperature Engineering: Third Information Exchange Meeting: Ibaraki-ken, Japan , 11-12 September 2003 (Nuclear Science)
The first screening tests in the CORALLINE facility were performed on wrought INCONEL 718 and HIP Udimet 720 (high-strength nickel-based superalloys, specially designed for large turbine blade fabrication), TZM, a molybdenum-based alloy with high creep resistance under inert atmosphere and Alloy 800 as a reference material (Table 1). s–1 nominal gas flow rate. Two helium-based gas mixtures were used with the following impurity concentrations: 100 ppm H2, 50 ppm CH4 and ~7 ppm H2O, named Atmosphere 1, and 195 ppm H2, 55 ppm CO, 20 ppm CH4 and ~2 ppm H2O (no deliberate addition), named Atmosphere 2.
Further discussion and modification of these requirements and properties is anticipated prior to the acceptance of the nuclear graphite materials specification. Table 1. m min Table 2. 15 max Table 3. Proposed chemical properties for nuclear grade graphite Property Ash content Chemical impurities – B Chemical impurities – Fe Chemical impurities – V Chemical impurities – Ti Chemical impurities – Ca Relative air oxidation rate Helium gas permeability ASTM test method C781 (C561) C781 (C560) C781 (C560) C781 (C560) C781 (C560) C781 (C560) C781 (C560) C781 Specification 1 000 ppm max 2 ppm max 100 ppm max 50 ppm max 50 ppm max 5 ppm max To be determined To be determined It is anticipated that additional property requirement will be added to the ASTM nuclear graphite materials specification as required by the draft ASME “CE” code: x additional chemical impurities: Si, Al, Ba, Cu, Ni, Sr; x boron equivalent; x Poisson’s ratio; x stress-strain curve (compressive); x surface area; x pore size distribution; x surface defects.
J. Marsden, “A New Specimen Geometry for the Iosipescu Shear Test”, to be presented at the 5th International Conference on Modern Practice in Stress and Vibration Analysis, Glasgow, UK, September 2003. L. Fok and G. Hall, “Comparison of UK, American and Japanese Unirradiated Graphite CTE Methodologies”, presented at the 18th Meeting of the Technical Working Group on Gas-cooled Reactors (TWG-GCR-18), Istanbul, Turkey, 16-18 June 2003. L. Fok and G. Hall, “Descriptions and Summary of National Programmes in Gas-cooled Reactors – United Kingdom”, presented at the 18th Meeting of the Technical Working Group on Gas-cooled Reactors (TWG-GCR-18), Istanbul, Turkey, 16-18 June 2003.
Basic Studies In The Field Of High Temperature Engineering: Third Information Exchange Meeting: Ibaraki-ken, Japan , 11-12 September 2003 (Nuclear Science) by Organization for Economic Cooperation &