Skip Nav Destination
1-6 of 6
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A004, August 8–12, 2022
Paper No: ICONE29-88944
... Abstract The cladding of the fuel rod is a cylinder-shaped structure made of Zirconium alloy, which will collapse due to structural creep under the extremely service conditions such as high temperature, high pressure, and high irradiation. The collapse of the cladding results in losing its...
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022
Paper No: ICONE29-90521
... Abstract Reactivity-initiated accident (RIA) is postulated design-basis accidents (DBAs) in light-water reactor (LWR). Moreover, Pellet-cladding mechanical interaction (PCMI) can cause a failure of the cladding in the early transient. In recent RIA regulatory guide released by NRC which points...
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A004, August 4–6, 2021
Paper No: ICONE28-63101
... operation. Therefore, this paper proposed a novel Dual-Cladding design concept to decrease the probability of cladding failure and increase the accident-tolerance ability of fuel rods in 200MW Nuclear Heating Reactor II (NHR200-II). Compared to the single cladding of conventional PWR fuel, the Dual-Cladding...
Eduard Usov, Nikolay Pribaturin, Vladimir Chukhno, Ilya Klimonov, Anton Butov, Ivan Kudashov, Albert Gafiyatullin, Pavel Lobanov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A031, August 4–5, 2020
Paper No: ICONE2020-16326
... calculation results are presented in the paper. The processes are investigated for the first phase of severe accidents covering the period from the onset of fuel-rod melting to the melt escape from the core center. Keywords: fuel pin degradation, melt, cladding, films, nitride fuel, metallic fuel, oxide fuel...
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A012, August 4–5, 2020
Paper No: ICONE2020-16674
...Abstract Abstract Pellet-Cladding Mechanical Interaction (PCMI) failure is the one of failure mode which must be evaluated in the nuclear fuel safety. PCMI is caused by the mechanical load to cladding due to the fuel pellet expansion. Under the high fuel burnup condition, the fuel cladding may...
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A029, July 29–August 2, 2013
Paper No: ICONE21-15876
... for million kilowatts SCWR (CSR1000) under development in China. Super Critical Water Cooled Reactor Water chemistry SCC susceptibility Corrosion rate Oxidation IGSCC Cladding ONGONGING RESEARCH OF WATER CHEMISTRY EFFECT ON SCC PROPERTIES OF CANDIDATE MATERIALS FOR SCWR GONG Bin Water Chemistry...