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Kim K.-S.,Korea Nuclear Engineering and Service Corporation | Kim J.-S.,Korea Nuclear Engineering and Service Corporation | Choi K.-S.,Korea Nuclear Engineering and Service Corporation | Shin T.-M.,Korea University | Yun H.-D.,Chungnam National University
Annals of Nuclear Energy | Year: 2010

Domestic and international regulations for the transportation of radioactive materials strictly prescribe the design requirements for spent nuclear fuel (SNF) transport casks. According to the applicable codes, a transport cask must withstand a free-drop impact of 9 m onto an unyielding surface and a free-drop impact of 1 m onto a mild steel bar. However, the structural performance of a transport cask is not easy to evaluate precisely because the dynamic impact characteristics of the cask, which includes impact limiters to absorb the impact energy, are so complex. In this study, a more advanced and applicable numerical simulation method using the finite element (FE) method via the commercial FE code LS-DYNA is proposed and verified against the experimental results for a 1/3-scale model of the KN-18 SNF transport cask, recently developed in Korea. In addition, the detailed dynamic impact characteristics of the transport cask under free-drop conditions are investigated via the proposed numerical simulation method and actual drop tests to improve the accuracy and optimization of the SNF transport cask design. © 2009 Elsevier Ltd. All rights reserved. Source


Kim K.-S.,Korea Nuclear Engineering and Service Corporation | Kim J.-S.,Korea Nuclear Engineering and Service Corporation | Choi K.-S.,Korea Nuclear Engineering and Service Corporation | Shin T.-M.,Korea University | Yun H.-D.,Chungnam National University
Annals of Nuclear Energy | Year: 2010

In Part 1 of this study, an advanced numerical simulation method was proposed to investigate the impact characteristics of the KN-18 spent nuclear fuel (SNF) transport cask recently developed in Korea and verified against the experimental results. In this study, sensitivity analyses are carried out using the proposed numerical simulation method to investigate the effects of the various modeling and design parameters, such as material model assumption, modeling methodology, analytical assumptions, and design variables that can affect the impact characteristics of a cask and the accuracy of the numerical results. These parametric analyses were also performed to provide a basis for correlations with test results that is closer to reality than merely conservative as a means of benchmarking the numerical models. In addition, the parametric analysis results are compared against the experimental results, and the sensitivities of each parameter are summarized to provide references for the future design and analysis of SNF transport casks. © 2009 Elsevier Ltd. All rights reserved. Source


Kim K.-S.,Korea Nuclear Engineering and Service Corporation | Chung S.-H.,Korea Hydro and Nuclear Power Co. | Kim J.-S.,Korea Nuclear Engineering and Service Corporation | Choi K.-S.,Korea Nuclear Engineering and Service Corporation | Yun H.-D.,Chungnam National University
Nuclear Engineering and Design | Year: 2010

Two new types of IP-2 (Industrial Package Type 2) to transport low and intermediate level radioactive waste (LILW) steel drums from nuclear power plants to a disposal facility have been developed in accordance with the IAEA and Korean regulations for radioactive materials. According to the regulations, both packages must preserve their structural performance after they are subjected to 0.9 m free drop tests, which are prescribed as normal conditions. In this study, an advanced analytical simulation and an evaluation process using the finite element (FE) method have been developed for the design assessment of the newly developed IP-2s. Then, analytical simulations for the various drop orientations were performed to evaluate the structural performance of the packages and demonstrate their compliance with the regulatory requirements. Also, full-scale drop tests were carried out to verify the numerical tools and modeling methodology used in the analyses and to confirm the performance of the IP-2s. In addition, parametric studies are carried out to investigate the sensitivity of the analytical variables, such as the material model and modeling methodology. In addition, this paper intends to provide basic guidance on the analytical simulation and evaluation process specifically for Korean types of transport packages, because numerous transport packages must now be developed for the various kinds of LILW that have accumulated in temporary storage facilities in Korea. © 2009 Elsevier B.V. All rights reserved. Source

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