• Korean Journal of Plant Taxonomy
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• v.46 no.4
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• pp.356-360
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• 2016

Ixora auricularis (Rubiaceae), previously recognized as endemic to Yunnan (China), was reported in Vietnam. This plant differs from the closely related species Ixora coccinea in its auriculate shape of the base leaf, greater number of secondary veins, shorter stipules, calyx having more appendices, shorter corolla tube, and the oblanceolata shape of the corolla tip. Detailed information about its description as well as illustrations, color photographs and a species key of related species of Ixora in Vietnam are provided.

• Korean Journal of Soil Science and Fertilizer
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• v.5 no.1
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• pp.1-8
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• 1972

In order to expect the effect of silica with large quantity application of current Fused calcium-magnesium phosphate on the paddy rice, there are difficulties of excess phosphorus application because of the high content of phosphate in this fertilizer. This experiment was discussed on the effect of posphate and silica absorbed by rice plant from the low concentrated fused calcium-magnesium phosphate which was fused with mixture of rock phosphate, chemical calcium oxide, magnesium oxide and silicate oxide in the furnace using coke, 1. The fusion material contained 8.9% of citric acid soluble $P_2O_5$ and 33% of soluble $SiO_2$. 2. The rice yields were increased with high significance accompanying the application levels of fused material amounts. 3. No. of grains per head, weight of 1,000 grains and percent of filled grain were caused to increase the productivity of rice plant on account of the high content of silica in straws absorbed from fusion material. The treatment of 300 kg/10a. was the highest yield among the levels of fusion material. 4. At the growing periods of rice plant, amount of absorbed phosphate was higher in the small amount treatment of fusion material until the formation period of young head, and was highest in the treatment of 300 kg/10a. leval among them but slightly desreased at 500 kg/10a. level at the harvest. Amount of absorbed silica was the same trend with phosphorus at the begining of growth period but increased rapidly from the formation period of young head to harvest in the large quantity application levels. 5. Much amount of nutrients were residued in the soil after experiment pacing with application levels. 6. The effect of silica and phosphate on rice plant can be expected with fusion material but it is necessary to decrease the phosphate content on account of the large residue of phosphate in the soil after experiment.

• Proceedings of the KSME Conference
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• 2007.05a
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• pp.108-113
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• 2007

In this report, stress corrosion cracking generation due to pipe material degradation in the primary stage of the nuclear power plant was investigated. Firstly, after artificially degrading the CF8A steel during 2, 4, and 6 months in actual temperature, $400^{\circ}C,$ assessed corrosion susceptibility of the degraded material following ASTM G5 standard. And next, the S.C.C. tests for the degraded material were conducted under the condition of $60^{\circ}C,$ 2wt.% H2BO3+Li70H solution, 0.8 oy. From the results, Corrosion rates linearly increased with degradation period and solution temperature increase. And both the raw material and the degraded materials were not failed in the S.C.C. test condition. In spite of long time test (about 3,900 hrs) under S.C.C. condition, surface pits or surface corrosion by the electro chemical reaction were not observed. And also, even though the nondestructive DCPD and ACPD methods were applied to on-line monitor the S.C.C. failure processes it was impossible because the surface pits and cracks were not generated.

• Elastomers and Composites
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• v.55 no.3
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• pp.222-228
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• 2020

Rubber materials, used in nuclear power plants, need high heat-oxidation resistance to curing or cracking under a heat aging environment. This is because they are applied to environments with high temperature, high humidity, and radiation exposure. Nuclear radiation causes additional hardening or degradation, therefore, rubber materials need radiation resistance that satisfies the general and any accidental conditions produced in the power plant. Therefore, in this study, we developed a rubber material with excellent heat and radiation resistance for the diaphragm seal of a nuclear steam generator nozzle dam. The rubber material greatly improved the reliability of the steam generator nozzle dam. In addition, 30 inch and 42 inch diaphragm seals were manufactured using the developed rubber material. A nozzle dam was installed in a nuclear power plant and tested under the same conditions as a steam generator to evaluate safety and reliability. In the future, the performance and safety of diaphragm seals developed through field tests of nuclear power plants will be evaluated and applied to currently operating and new nuclear power plants.

• Journal of Environmental Science International
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• v.32 no.11
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• pp.821-831
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• 2023

Recently, landscaping construction has played a significant role in enhancing the quality of life for citizens by creating and maintaining outdoor spaces. However, landscaping projects vary in material procurement depending on the contracting method, and they also present various challenges in defect occurrence and defect rectification due to their specialized nature. In this study, we classified different types of projects based on material procurement ratios and conducted on-site assessments of defect status by specific processes. We also analyzed the itemization of material ratios and defect rectification costs. The results revealed it was found that projects with a higher proportion of government-provided materials had the poorest defect status in terms of planting works and also incurred the highest defect rectification costs. Moreover, conflicts concerning the responsibility for defects arose. Currently, there are no specific guidelines for setting standards for the proportion of government-provided materials in landscaping construction contracts. Furthermore, there is ambiguity in the management of defect rectification. Therefore, it is necessary to establish a systematic landscaping construction contracting framework by providing institutional guidelines tailored to local governments or the circumstances of contracting entities and to conduct thorough reviews of construction processes.

• Journal of Korean Society of Water and Wastewater
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• v.14 no.3
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• pp.231-239
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• 2000

Water treatment processes produce sludges resulting from water clarification. Sludge production amount increases each year and its treatment and disposal is growing to social problems according to water demand increase. Water treatment plant sludges can be modified to soil cover in sanitary landfill site through the lime treatment. Compression strength of $1.0kg/cm^2$ or more is recommended for soil cover material in municipal landfilling site. Compression and shear strength properties of modified sludges showed material property improvement applicable for soil cover alternatives. Solidification effect of the modified sludge was observed through the scanning electron microscope. Extraction tests for hazardous components in sludges revealed that extraction levels of cadmium, copper, and lead were below the regulated criteria. When adding 10% calcium hydroxide to water treatment plant sludges, the modified sludges can reach material properties for cover soil after 28 days solidification reaction.

• Transactions of the Korean Society of Mechanical Engineers
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• v.19 no.5
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• pp.1182-1189
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• 1995

Several methods have been developed to predict the creep rupture time of the steam pipes in thermal power plant. However, existing creep life prediction methods give very conservative value at operating stress of power plant and creep rupture strain cannot be well estimated. Therefore, in this study, creep rupture time and strain prediction method accounting for material damage and grain boundary sliding is newly proposed and compared with the existing experimental data. The creep damage evolves by continuous cavity nucleation and constrained cavity growth. The results showed good correlation between the theoretically predicted creep rupture time and the experimental data. And creep rupture strain may be well estimated by using the proposed method.

• Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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• 2000.10a
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• pp.42-46
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• 2000

In this paper, joints of Cu-1Cr-0.1Zr alloy to STS316L were performed by friction welding method. Cu-1Cr-0.1Zr alloy is attractive candidate as nuclear power plant material and exibit the best combination of high sts good electrical and thermal conductivity of any copper alloy examined. The stainless steel is a structural material who alloy acts as a heat sink material for the surface heat flux in the first wall. So, in this paper, not only the develop optimizing of friction welding with more reliability and more applicabililty but also the development of in-process rear quility(such as strength and toughness) evaluation technique by acoustic emission for friction welding of such nuclear component of Cu-1Cr-0.1Zr alloy to STS316L steel were performed.

• Proceedings of the KSME Conference
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• 2000.11a
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• pp.193-198
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• 2000

The small punch test have been developed to evaluate the material strength of the power plant components. This small punch test specimen is very small than the conventional strength test specimens. Korea Electric Power Research Institute (KEPRI) have been applying this test to assess accurately the life of thermal power plant and enhancing the reliability. The small punch test for gas turbine blades is under development. It's possible to compare the relative strength among the same materials having different operation histories. In this paper, the strength reductions of gas turbine materials are investigated by the small punch tests. All materials shows the almost same strength and deformation with the allowable deviation. At the same test temperature, the damaged material has the maximum load value. The strength reduction is not shown in this small punch test results.

• Journal of the Korean Institute of Electrical and Electronic Material Engineers
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• v.14 no.5
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• pp.397-404
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• 2001

This study describes the effect of γ-ray irradiation on the properties of insulation materials for low voltage cables in a nuclear power plant. The radiation effects were characterized by measuring OIT, FTIR, electrical properties of the irradiated specimens. As a result, they showed the decrease of OIT and the increase of chemical structural defects with the increase of γ-ray amount. Also, the electrical properties such as dielectrical constant, tan $\delta$ and current were changed by aging. These changes may come from the increase of chemical structural defects by $\delta$-ray irradiation.