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박종만,탁영욱,정용진,이규홍,김희문,정양홍,유병옥,진영관,서철교,양성우,김현정,임정식,YEON SOO KIM,Bei Ye,Gerard L. Hofman 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.5
The construction project of the Kijang research reactor (KJRR), which is the second research reactor in Korea, has been launched. The KJRR was designed to use, for the first time, U-Mo fuel. Plate-type U-7 wt.% Mo/Ale5 wt.% Si, referred to as U-7Mo/Ale5Si, dispersion fuel with a uranium loading of 8.0 gU/ cm3, was selected to achieve higher fuel efficiency and performance than are possible when using U3Si2/ Al dispersion fuel. To qualify the U-Mo fuel in terms of plate geometry, the first miniplates [HANARO Miniplate (HAMP-1)], containing U-7Mo/Ale5Si dispersion fuel (8 gU/cm3), were fabricated at the Korea Atomic Energy Research Institute and recently irradiated at HANARO. The PIE (Post-irradiation Examination) results of the HAMP-1 irradiation test were analyzed in depth in order to verify the safe in-pile performance of the U-7Mo/Ale5Si dispersion fuel under the KJRR irradiation conditions. Nondestructive analyses included visual inspection, gamma spectrometric mapping, and two-dimensional measurements of the plate thickness and oxide thickness. Destructive PIE work was also carried out, focusing on characterization of the microstructural behavior using optical microscopy and scanning electron microscopy. Electron probe microanalysis was also used to measure the elemental concentrations in the interaction layer formed between the U-Mo kernels and the matrix. A blistering threshold test and a bending test were performed on the irradiated HAMP-1 miniplates that were saved from the destructive tests. Swelling evaluation of the U-Mo fuel was also conducted using two methods: plate thickness measurement and meat thickness measurement.
Drop Impact Analysis of Plate-type Fuel Assembly in Research Reactor
김현길,임정식,이병호,오재용,탁영욱 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.4
In this research, a drop impact analysis of a fuel assembly in a research reactor is carried out to determine whether thefuel plate integrity is maintained in a drop accident. A fuel assembly drop accident is classified based on where the accidentoccurs, i.e., inside or outside the reactor, since each occasion results in a different impact load on the fuel assembly. Ananalysis procedure suitable for each drop situation is systematically established. For an accident occurring outside the reactor,the direct impact of a fuel assembly on the pool bottom is analyzed using implicit and explicit approaches. The effectsof the key parameters, such as the impact velocity and structural damping ratios, are also studied. For an accident occurringinside the reactor, the falling fuel assembly may first hit the fixing bar at the upper part of the standing fuel assembly. Toconfirm the fuel plate integrity, a fracture of the fixing bar should be investigated, since the fixing bar plays a role in protectingthe fuel plate from the external impact force. Through such an analysis, the suitability of an impact analysis procedureassociated with the drop situation in the research reactor is shown.