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تعداد نتایج: 7548  

Journal: :Journal of Nuclear Materials 2022

Outcomes of an activity on development and verification models for Fission Gas Release in Light-Water Reactor fuels during Loss-of-Coolant Accidents are described. The GRSW-A model the FALCON code is extended to simulate processes fuel fragmentation concomitant transient Release. FRELAX redesigned with a view simulation bulk flow diffusion gases rod free volume. Finally, close coupling updated ...

Journal: :Journal of Nuclear Materials 2022

Cr-coated Zr-alloys are a near-term cladding concept to improve reactor safety during accident scenarios. Burst and steam oxidation behavior of bare Zirlo claddings were examined under simulated loss-of-coolant conditions. The 4.4 µm coating had no substantial effect on ballooning or opening geometry but did increase burst temperatures at higher pressures. reduced the compared specimens, in reg...

Journal: :Journal of Nuclear Science and Technology 1995

Journal: :Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 1984

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