Nuclear Fuel Modelling During Power Ramp

نویسندگان

چکیده

Fuel rods operating for several years in a LWR can experience fuel-cladding gap closure as result of the phenomena due to temperature and irradiation. Local power increase induces circumferential stresses cladding different expansion pellet. In presence corrosive fission products (i.e. Iodine) beyond specific stress threshold level burnup, cracks may grow-up from internal external surface, causing fuel rod failure. The phenomenon, known pellet interaction-stress corrosion cracking PCI/SCC, or PCI, has been identified problem since 70's. PWR Super-Ramp experiment (part OECD/NEA “International Performance Experiments (IFPE) database”) twenty eight behaviour simulated using TRANSURANUS code version “v1m1j11”. Two sets (“Reference” “Improved”) suitable input decks modelling rods, based on available literature are used run simulations. Focus is given main which involved influence Systematic comparison results with experimental data performed parameters relevant PCI phenomenon. Sensitivity calculations gas release models implemented also order address impact results. show ability “v1m1j11” conservatively predicting failure Zircaloy-4 cladding. Increased availability would help perform deeper analysis.

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ژورنال

عنوان ژورنال: Energija

سال: 2022

ISSN: ['0354-8651', '2812-7528']

DOI: https://doi.org/10.37798/2013621-4219