• Safe Food
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• v.6 no.2
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• pp.40-46
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• 2011

• Proceedings of the Korea Concrete Institute Conference
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• 2006.11a
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• pp.917-920
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• 2006

This paper reports a comparative study for performance evaluation guidelines for bridge bearings. Guidelines for bridge bearings such as KS, EN1337, AASHTO LRFD, and Japanese code were analyzed. In addition, fatigue tests of elastomeric bearing are being conducted for allowable shear deformation and compressive stress. Based on literature survey and tests, the innovative concept of performance evaluation guidelines for bridge bearings is suggested.

• Proceedings of the Korea Concrete Institute Conference
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• 2002.10a
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• pp.179-184
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• 2002

The evaluation equation of torsional moment for prestressed concrete members in ACI 318-95 ignores the contribution of concrete, T$_{c}$. Several research indicates that the current ACI code is not successful in predicting the observed torsional moment of the PSC beams with reasonable accuracy. This paper proposes an evaluation equation of torsional moment taking into account the inter-effects between concrete and torsional reinforcement on the torsional resistance of the PSC beams. According to the comparison with the 31 test results, the torsion equation in ACI code underestimated or overestimated the real torsional moment of prestressed concrete beams. On the other hand, the proposed torsional equation is shown to be in a good agreement with experimental results.s.

• Proceedings of the KSR Conference
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• 2007.05a
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• pp.155-161
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• 2007

A bogie frame is typical safty part of railway vehicle. Main performance of a bogie frame is to support a car body and passenger weight and transfer traction and braking force. This paper is to evaluate the static strength and fatigue strength for the end trailer bogie with UIC 615-4 code. Therefore stress analysis of the end trailer bogie frame has been performed for various loading condition according to the UIC 615-4 code and haigh diagram is used for evaluation of fatigue strength. By the results of these analysis, static and fatigue strength of the end trailer bogie is satisfied with a applied criterion.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.795-801
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• 1998

Metallic fatigue of Pressurized Water Reactor(PWR) materials is a generic safety issue for commercial nuclear power plants. It is very important to obtain the fatigue usage factor for component integrity and life extension. In this paper, fatigue usage was obtained at the inside surface of Kori unit 2, 3 and 4 RCP casing weld, based on the design transient. And it was intended to establish the procedure and the detailed method of fatigue evaluation in accordance with ASME Section III Code. According to this code rule, two methods to determine the stress cycle and the number of cycles could be applied. One method is the superposition of cycles of various design transients and the other is based on the assumption that a stress cycle correspond to only one design transient. Both method showed almost same fatigue usage in the RCP casing weld.

• Proceedings of the Korean Society for Technology of Plasticity Conference
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• 2008.05a
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• pp.387-390
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• 2008

Electromagnetic forming (EMF) technology, which is one of the high speed forming methods, has been used for the forming process in various industry fields. Numerical approach by finite element simulation of the EMF process is presented in this study. The implicit code is used to obtain the numerical model of the time-varying currents that are discharged through the coil in order to obtain the transient magnetic forces. In addition, the body forces generated in the workpiece are used as the loading condition to analyze deformation of thin sheet metal workpiece using explicit code. Numerical approach for a dimpled shape by EMF process is carried out and the simulated results of the dimpled shape by EMF are reviewed in view of the deformed shape and formability evaluation.

• Nuclear Engineering and Technology
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• v.54 no.5
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• pp.1781-1788
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• 2022

The containment building Kori Unit 1 may require sequential steps for full decommissioning. This study assumes that the containment building is to be used as an auxiliary building that handles nuclear power systems and materials during decommissioning before conversion into a greenfield. Through the derivation of guidelines and dose evaluation, it was confirmed whether the radiation workers were satisfied with the ALARA decision. The specific modeling of the external radiation exposure was performed based on the facility investigation procedures. The external radiation specific derived concentration guideline levels (DCGLs) for radiation workers in containment building were obtained using the RESRAD-BUILD code and were applied to the VISIPLAN 3D ALARA Planning Tool code to calculate the working dose and check worker safety. The derivation of site-specific and realistic DCGLs and dose evaluation via 3D modeling can contribute to the scenario development for the decommission and remediation of containment building.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.32 no.3
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• pp.102-110
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• 2004

A design code validated against the thermal analysis results of CFD and published RTE code for a regeneratively cooled combustion chamber has been developed. The major function of the code is to predict the regenerative cooling performance and stress of the chamber wall. Adopted are the empirical correlation for the evaluation of the heat transfer coefficient of hot gas and coolant, and theoretical formula for the fin effect of the channel rib. The hot-gas-side wall temperature from the present code shows 100 K difference at most compared to RTE results. It shows less than 10 % difference for the heat flux thrall through the chamber wall and hot-gas-side convective heat transfer coefficient. The major cause of the wall temperature difference is due to the underestimation of the fin effect of the channel rib.

• Nuclear Engineering and Technology
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• v.38 no.1
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• pp.45-60
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• 2006

Presently, the VHTGR (Very High Temperature Gas-cooled Reactor) is considered the most attractive candidate for a GEN-IV reactor to produce hydrogen, which will be a key resource for future energy production. A new concept for a reactor cavity cooling system (RCCS), a critical safety feature in the VHTGR, is proposed in the present study. The proposed RCCS consists of passive water pool and active air cooling systems. These are employed to overcome the poor cooling capability of the air-cooled RCCS and the complex cavity structures of the water-cooled RCCS. In order to estimate the licensibility of the proposed design, its performance and integrity were tested experimentally with a reduced-scale mock-up facility, as well as with a separate-effect test facility (SET) for the 1/4 water pool of the RCCS-SNU to examine the heat transfer and pressure drop and code capability. This paper presents the test results for SET and validation of MARS-GCR, a system code for the safety analysis of a HTGR. In addition, CFX5.7, a computational fluid dynamics code, was also used for the code-to-code benchmark of MARS-GCR. From the present experimental and numerical studies, the efficacy of MARS-GCR in application to determining the optimal design of complicated systems such as a RCCS and evaluation of their feasibility has been validated.

• International Journal of High-Rise Buildings
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• v.1 no.3
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• pp.211-220
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• 2012

The current 2002 Indonesian Seismic Code consists of prescriptive criteria that are intended to result in buildings capable of providing certain levels of performance. However, the actual performance capability of buildings is not assessed as part of the code procedures. Several analysis procedures are allowed, and the state of practice is to use the RSA with six-zone seismic map developed for 475-year earthquake. This code is being revised and will adopt many of the ASCE7-10 provisions and 2475-year earthquake for MCE. The growth of tall buildings compels engineers to look for more optimal lateral system. The use of RC core wall as single system has been adopted by very few engineering firms, which is allowed in the current code but will no longer be the case if the new one is in effect. Other innovative structural system such as core wall and outrigger is not addressed in the proposed new code. Engineers must then resort to NLRHA. Currently, one 50-story building under construction using RC core wall and outrigger has been designed with RSA and employing capacity design principles, then evaluated using NLRHA per TBI Guidelines. Based on the evaluation, the performance of the 50-story building generally still meets the criteria of the TBI Guidelines. The result of the case study is presented in this paper.