• The Journal of the Korea Contents Association
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• v.17 no.10
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• pp.598-615
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• 2017

This paper compares the sources of the changes in the production of manufacturing industry between Korea and Japan during year 2000 ~year 2011 by I-O SDA. The results show that the first source of the increase in the production of Manufacturing industry in Korea is export, while in Japan the technological change. However, the contribution of technological change is relatively small in Korea and moreover decreasing. Meanwhile, the domestic final demand is the second source of the increase in the production of Korean manufacturing industry, but it was the first source of the decrease in the production of Japanese counterpart. On the other hand, the decrease in import substitution for both the intermediate and domestic final goods is significantly contributed to the decrease in the production of both Korean and Japanese manufacturing industry. Conclusively, these results confirm that the growth of Korean manufacturing industry has heavily depended on export. Then, considering the current global economic environment that is rapidly becoming more uncertain as well as volatile, the results imply that the heavy export dependence may become a key hurdle for the solid sustained growth of Korean manufacturing industry, so that policy ensuring more evenly balanced growth contribution from all growth sources is necessary. In particular, policy to promote technological change and import substitution is required with greater weight.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.41-50
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• 2006

In this paper, sets of engineering analyses were conducted to renew the overall dimensions and configurations of a disposal container proposed as a prototype in the previous study. Such efforts and calculation results can provide new design variables such as the inner basket array type and thickness of the outer shell and the lid & bottom of a spent nuclear fuel disposal container. These efforts include radiation shielding and nuclear criticality analyses to check to see whether the dimensions of the container proposed from the mechanical structural analyses can provide a nuclear safety or not. According to the results of the structural analysis of a PWR disposal container by varying the diameter of the container insert, the Maximum Von Mises stress from the 102 cm-container meets the safety factor of 2.0 for both extreme and normal load conditions. This container also satisfies the nuclear criticality and radiation safety limits. This decrease in the diameter results in a weight loss of a container by $\sim20$ tons.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.37-43
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• 2012

Radioactive waste transport package was developed to transport eight drums of low and intermediate level waste(LILW) in accordance with the IAEA and domestic related regulations. The package is classified with industrial package IP-2. IP-2 package is required to undergo a free drop test and a stacking test. After free drop and stacking tests, it should prevent the loss or dispersal of radioactive contents, and loss of shielding integrity which would result in more than 20 % increase in the radiation level at any external surface of the package. The objective of this study is to establish the safety test method and procedure for stacking test and to prove the structural integrities of the IP-2 package. Stacking test and analysis were performed with a compressive load equal to five times the weight of the package for a period of 24 hours using a full scale model. Strains and displacements were measured at the corner fitting of the package during the stacking test. The measured strains and displacements were compared with the analysis results, and there were good agreements. It is very difficult to measure the deflection at the container base, so the maximum deflection of the container base was calculated by the analysis method. The maximum displacement at the corner fitting and deflection at the container base were less than their allowable values. Dimensions of the test model, thickness of shielding material and bolt torque were measured before and after the stacking test. Throughout the stacking test, it was found that there were no loss or dispersal of radioactive contents and no loss of shielding integrity. Thus, the package was shown to comply with the requirements to maintain structural integrity under the stacking condition.

• Computers and Concrete
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• v.22 no.3
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• pp.337-353
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• 2018

The present study focuses on examining the structural behaviour of steel-fibre-reinforced concrete (SFRC) beams under high rates of loading largely associated with impact problems. Fibres are added to the concrete mix to enhance ductility and energy absorption, which is important for impact-resistant design. A simple, yet practical non-linear finite-element analysis (NLFEA) model was used in the present study. Experimental static and impact tests were also carried out on beams spanning 1.3 meter with weights dropped from heights of 1.5 m and 2.5 m, respectively. The numerical model realistically describes the fully-brittle tensile behaviour of plain concrete as well as the contribution of steel fibres to the post-cracking response (the latter was allowed for by conveniently adjusting the constitutive relations for plain concrete, mainly in uniaxial tension). Suitable material relations (describing compression, tension and shear) were selected for SFRC and incorporated into ABAQUS software Brittle Cracking concrete model. A more complex model (i.e., the Damaged Plasticity concrete model in ABAQUS) was also considered and it was found that the seemingly simple (but fundamental) Brittle Cracking model yielded reliable results. Published data obtained from drop-weight experimental tests on RC and SFRC beams indicates that there is an increase in the maximum load recorded (compared to the corresponding static one) and a reduction in the portion of the beam span reacting to the impact load. However, there is considerable scatter and the specimens were often tested to complete destruction and thus yielding post-failure characteristics of little design value and making it difficult to pinpoint the actual load-carrying capacity and identify the associated true ultimate limit state (ULS). To address this, dynamic NLFEA was employed and the impact load applied was reduced gradually and applied in pulses to pinpoint the actual failure point. Different case studies were considered covering impact loading responses at both the material and structural levels as well as comparisons between RC and SFRC specimens. Steel fibres were found to increase the load-carrying capacity and deformability by offering better control over the cracking process concrete undergoes and allowing the impact energy to be absorbed more effectively compared to conventional RC members. This is useful for impact-resistant design of SFRC beams.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.153-162
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• 2005

In this Paper, sets of engineering analyses were conducted to renew the overall dimensions and configurations of a disposal container proposed as a prototype in the previous study. Such efforts and calculation results can provide new design variables such as the inner basket array type and thickness of the outer shell and the lid & bottom of a spent nuclear fuel disposal container. These efforts include radiation shielding and nuclear criticality analyses to check to see whether the dimensions of the container proposed from the mechanical structural analyses can provide a nuclear safety or not. According to the results of the structural analysis of a PWR disposal container by varying the diameter of the container insert, the Maximum Von Mises stress from the 102 cm container meets the safety factor of 2.0 for both extreme and normal load conditions. This container also satisfies the nuclear criticality and radiation safety limits. This decrease in the diameter results in a weight loss of a container by ${\~}$20 tons.

• Microbiology and Biotechnology Letters
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• v.22 no.2
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• pp.190-196
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• 1994

Alkali soluble(AS) fraction, revealed the highest antitumor activity of the alkali extracted fractions of G. lucidum IY 009, was loaded on DEAE cellulose(OH$^{-}$ form) column. AS-1, AS-2, AS-3, AS-4 and AS-5 were obtained by stepwise elution with H$_{2}$O, 0.1 M NaHCO$_{3}$, 0.3 M NaHCO$_{3}$, 0.5 M NaHCO$_{3}$ and 0.5 N NaOH respectively, and their antitumor activities(I.R. %) against the sarcoma 180 were 97.5%, 68.0%, 73.0%, 81.0% and 66.0% respectively. AS-1 observed highest antitumor activity was appeared as single peak on the Sepharose CL-4B column chromatography, and their molecular weight was about 580,000 dalton. The carbohydrate content of AS-1 was 98.9%, their monosaccharide consisted of 67.5% of mannose, 22.5% of xylose, 5.8% of glucose, 1.8% of galactose and 2.0% of ribose. AS-1 was assumed $\alpha $linkaged xylomannan having infrared absorption at 864.3 cm$^{-1}$. The main alditol acetates of AS-1 were identified as 1,5-Di-O-acetyl1-2,3,4-Tri-O-methylxylitol, 1,4,5-Tro-O-acety1-2,3,6-Tri-O-methylmannitol and 1,3,4,5-Tetra-O-acety1-2,6-Di-O-methylmannitol by methylation analysis, and their molar ratio was 1 : 2 : 1. The core portion of AS-1 might be $\alpha $-(1$\longrightarrow $ 4)mannopyranosyl unit branched with side chain, C1 of xylopyranosyl residue linked to C3 of every 3 mannopyranosyl units, and the degree of polymerization of structural unit in AS-1 was about 835.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.18 no.1
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• pp.210-215
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• 2017

This study examined the mechanical design and the structural strength analysis of the rake used in a rotary screener. For the case of the mid-water part, an additional load condition was given by calculating the underwater frictional force generated by the water. For the upper-water part, the analysis was done by dividing the 500kg additional load into the left-concentrated load, center-concentrated load, and right-concentrated load depending on the location of the attached narrow material, and it was determined that all 3 additional load conditions were free from plastic deformation and were secure. The additional load that can occur from the weight of the attached narrow material was divided into three, 1,000kg, 1,300kg, and 1,500kg, and then analyzed. The results of the analysis show that in the case of 1,000kg and 1,300kg, an equivalent strength of 143.6MPa and 186.6MPa occurred, respectively. These figures are lower than the yield strength of the STS304 used in the rotary screener. Therefore, plastic deformation does not occur and is considered to be secure. In the case of 1500kg, however, the equivalent strength that occurred was 215.41MPa, which is greater than the yield strength of STS304, and was judged to be unsafe.

• Journal of Navigation and Port Research
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• v.43 no.6
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• pp.444-449
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• 2019

The "Standard on Cargo Stowage and Securing" implemented to safely stow and secure the cargo of international shipping vessels and domestic car ferries, has also been applied to general cargo ships transported between domestic ports since J anuary 2018. As a result, a new type of cargo, such as a non-standardized steel box transported by general cargo ships to major ports in Korea from Jeju Island in Korea, must be factored as the method of safe stowage and securing according to the legal classification of cargo. This study analyzed the legal status of a steel box by analyzing the actual size, shape of steel box through field verification, collection of data from relevant agencies and finally proposed the methods of safe stowage and securing for a steel box in the cargo holds of general cargo ships. According to the relevant domestic laws and international regulations, steel boxes could be classified as pallette boxes with protective outer packing, a type of non-standardized cargo. Additionally, when a steel box is loaded into the cargo hold of general cargo ships, a method of loading and transporting them must be factored so that there is no gap in the cargo hold of ships. Verification of the safety of the tightly loading and transportation measures in the reviewed cargo hold was verified through safety of the hull structure and securing of the ship's stability. As a result of verification of the safety of the hull structure, the value of the structural strength on both sides and the floor of the cargo hold for the total weight of cargo that can be loaded in the cargo hold was satisfied, and the value of the ship's stability was satisfied with the value of GoM and the restoration of the three cross-sectional stability curve areas.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.18 no.3
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• pp.694-702
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• 2017

In the case of an elevated railway station, structure borne noise and vibration due to structural limitations allow the load and vibration from railway vehicles to be directly transmitted to the station structure, resulting in an increase in the number of civil complaints from customers and staff of the station. The floating slab track system, which is well known as one of the solutions for reducing the noise and vibration from elevated railway stations, usually contains rubber mounts or rubber pads under the railway slab which act as a damper. These types of device have the disadvantage that is difficult to predetermine the exact stiffness and damping ratio under the nonlinear loads resulting from train services. In this study, an isolator with a friction type of wedge is introduced, which can be applied to floating slab track systems and to be designed with precisely the required stiffness. Furthermore, a comparative analysis of the stiffness between the designed and experimental values is carried out, while the damping ratio, which is closely related to the friction wedge blocks, is deduced according to the train load condition. The performance tests of the isolator were conducted in accordance with the DIN 45673-7 standard which includes both static and dynamic load tests. The load conditions for the performance tests are designed to conform to the DIN standard related to the weight of the train and rail track, in order to perform vertical and horizontal load tests, so as to ensure the secure structural safety of the railway. Also, by checking the change aspect of the friction coefficients of the friction elements according to the loading rate, the vibration reduction performance of the friction type isolator with variable loading rate conditions is examined.

• Resources Recycling
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• v.22 no.2
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• pp.62-70
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• 2013

Electric arc furnace slag is made in ironworks during steel refining, it is been increasing chemical and physical resistibility using ageing method of unstable state of melting steel slag for using concrete's fine aggregates. Which is been changing stable molecular structure of aggregates, it restrains moving of ion and molecule. In Korea, KS F 4571 has been prepared for using the electric arc furnace slag to concrete aggregates. In this study, Electric arc furnace slag is used in the PMC(Polymer Modified Concrete) which is applied a bridge pavement of rehabilitation, largely. In that case, this study evaluates the structural safety about increasing the specific weight. The 4-type bridges(RC slab bridge, RC rigid-frame bridge, PSC Beam bridge, Steel box girder bridge) pavement's increasing the total dead load is in 1 ~ 2%. Design moments in a load combination are increased less then 2%. safety factor is decreased less than 3%. Therefore, the structural safety has no problem for applying the electric arc furnace slag within PMC in bridge.