MECHANICAL STUDY OF 9Cr-316SS-1Mo MATERIALS FOR NUCLEAR FUEL CLADDING MATERIALS POWER REACTORS
نویسندگان
چکیده
Cladding or cladding used for nuclear fuel elements requires special requirements such as good mechanical properties, radiation resistance, corrosion adequate physical and chemical low thermal neutron absorption. Materials that are widely structural materials reactors beryllium, magnesium, aluminum, zirconium their alloys. Alloy 9Cr-316-1Mo Nuclear material. material has been made. The was chosen an alternative because it properties with a microscopic cross-section of 2.6 barn. At first, the sample cast withThe composition is 90% 316L Stainless Steel, 9% Chromium (Cr) 1% Molybdenum (Mo) added using electric arc. After casting alloy,the tested without heating then given heat treatment (tempering) starting from 100 0C, 200 300 400 0C 500 allowed to stand 60 minutes, hardness (rockwell) , Impact testing, micro structure testing Chemical (XRF). results Rockwell test obtained highest value in tempering, namely 20.66 HRc lowest tempering 16.33 HRc. Then impact energy which 0.9996 Joule/mm2 0.9962 Joule/mm2. microstructure showed still contained ferrite, pearlite martensite. process not fully completed will be reported later.
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ژورنال
عنوان ژورنال: International Journal of Innovation in Mechanical Engineering and Advanced Materials
سال: 2023
ISSN: ['2477-5428', '2477-541X']
DOI: https://doi.org/10.22441/ijimeam.v4i2.16832