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Evaluation of axial and tangential ultimate tensile strength of zirconium cladding tubes
Marton Kiraly,Daniel Mihaly Antok,Laszlone Horvath,Zoltan Hozer 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.3
Different methods of axial and tangential testing and various sample geometries were investigated, andnew test geometries were designed to determine the ultimate tensile strength of zirconium claddingtubes. The finite element method was used to model the tensile tests, and the results of the simulationswere evaluated. Axial and tangential tensile tests were performed on as-received and machined fuelcladding tube samples of both E110 and E110G Russian zirconium alloys at room temperature to comparetheir ultimate tensile strengths and the different sample preparation methods
Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes
Kiraly, Marton,Horvath, Marta,Nagy, Richard,Ver, Nora,Hozer, Zoltan Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.9
The mechanical interaction between the fuel pellet and the cladding tube of a nuclear fuel rod is a very important for safety studies as this phenomenon could lead to fuel failure and release of radioactivity. To investigate the ductility of cladding tubes used in WWER type nuclear power plants, several mandrel tests were performed in the Centre for Energy Research (EK). This modified mandrel test was used to model the mechanical interaction between the fuel pellet and the cladding using a segmented tool. The tests were conducted at room temperature and at 300 ℃ with inactive as-received and hydrogenated cladding ring samples. The results show a gradual decrease in ductility as the hydrogen content increases, the ductile-brittle transition was seen above 1500 ppm hydrogen absorbed.