• KEPCO Journal on Electric Power and Energy
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• 제7권1호
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• pp.125-128
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• 2021

This paper presents the root cause failure analysis of the circulating water pump in the 560 MW thermal power plant. A fractured austenitic stainless-steel shaft operated for 24 years was examined. Fracture morphology was investigated by micro and macro-fractographic analysis. The metallurgical analyses including chemical analysis, metallography and hardness testing were performed. The analysis reveals that the pump shaft was fractured due to the reverse bending load with combination of rotating bending load. Corrective actions for plant operator was recommended based on the analysis.

• Journal of Korean Society on Water Environment
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• 제22권6호
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• pp.1137-1143
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• 2006

In this study we investigated the removal characteristics of NOM and bromate formation characteristics in SOMT reactor. The system was recently developed as a novel ozone reactor and installed in SJ pilot plant. DOC values were decreased within 3% after treatment of 0.5~2.0 mg/L ozone dosage in SOMT reactor while the $UV_{254}$ value was 69% decreased at 2.0 mg/L ozone dosage. The composition of NOM was analysed by LC-OCD (Organic Cabon Detector) after ozone treatment in SOMT reactor to elucidate the variation of NOM character. Polysaccharide (more than 20,000 g/mol) fraction of NOM was decomposed while building blocks (350~500 g/mol) and neutral (less than 350 g/mol) fraction increased. Spiked bromide reacted with 0.5~2.0 mg/L ozone dosage in the SOMT reactor. The bromate formation was proportional to the ozone dosage ($R^2=0.978$) but not proportional to reaction time. The maximum concentration of formated bromate was not exceeded to 10% of spiked bromide concentration.

• Journal of Korean Society for Atmospheric Environment
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• 제23권6호
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• pp.689-698
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• 2007

Particular attention is paid to the validity of PM-10 measurement using beta attenuation method. In this study, the inter-comparison studies were undertaken for PM-10 sampler with different measuring methods. The three beta attenuation monitoring instruments (BAM1020, FH C-14, and DIGS-150) and filter based gravitational method using High Volume Air Sampler were collocated and mass concentrations were compared from August to November, 2006. The results of the investigation show that beta attenuation monitoring instruments are comparable with gravitational method within 10% of measurement error. For specific conditions under high humidity and high concentrations, the inter-comparison results also showed a relatively good agreement and this can be explained as the effect of inlet heating of beta attenuation instrument. Subsequently, this study shows that beta attenuation monitoring instruments can be equivalently used with reasonable validity when compared gravimetric method.

• Journal of the Korean Society of Safety
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• 제23권6호
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• pp.76-83
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• 2008

In the course of increasing in human and material damage caused by fire, it is an important research field to develop clean extinguishing agent which does no harm to global environment as well as has a good extinguishing efficiency. This research is a basic step to develop a new clean extinguishing agent. In order to get a satisfactory result, we tested fire extinguishing ability using nitrogen and Novec mixtures gas which are inert gas and new clean extinguishing agent. We used Cup Burner Test made by international standard ISO-14520 regulations of gaseous extinguishing agent ability test, and the fuels used in the test are n-heptane, methanol, ethanol, iso-propanol and 1-butanol. The experimental results of flame extinguishing concentration are n-heptane 6.54%, methanol 8.47%, ethanol 6.98%, isopropanol 6.10% and butanol 6.54% by pure Novec agent. So the finding is that a new clean agent, Novec has an efficient extinguishing ability in a state of gas. Also, in a test as to mixtures gas of nitrogen and Novec, it has a good result for minimum oxygen concentration is under 16%.

• Journal of Korean Society on Water Environment
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• 제23권2호
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• pp.201-205
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• 2007

This paper reports the amount of $^{222}Rn$ and $^{238}U$ in 18 sites of ground water and 30 sites of surface water. The instrument used to count $^{222}Rn$ activity was the liquid scintillation counter (LSC) which could resolute ${\alpha}$ and ${\beta}$ radiations. And $^{238}U$ was analyzed by the inductively coupled plasma (ICP). Radon and Uranium were not detected in raw and treated water which were sampled in a water treatment plant. However, radon ($^{222}Rn$) was high concentration in ground water from Jeon-la, Gang-won. So was uranium ($^{238}U$) in case of ground water from Gang-won, Choong-chung. Radon ($^{222}Rn$) activities were detected less than 15 pCi/L at 5 sampling points, 15~300 pCi/L at 7 sampling points, 300~4000 pCi/L at 6 sampling points. However, Radon ($^{222}Rn$) activities of all ground water samples were less than 4,000 pCi/L, which was bellow American Alternative Maximum Contamination Level (AMCL). Uranium ($^{238}U$) concentrations were less than $0.1{\mu}g/L$ at 5 sampling points, from $0.1{\mu}g/L$ to $20{\mu}g/L$ at 13 sampling points. Uranium was not detected in about 30% of the whole samples, but the concentration ranged from relatively low to high concentrations depending on the sampling point. The minimum detectable activity (MDA) of radon was 15 pCi/L. and the detection limit of uranium was $0.1{\mu}g/L$.

• Journal of Korean Society of Occupational and Environmental Hygiene
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• 제4권1호
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• pp.33-42
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• 1994

This study was carried out to assess worker exposure to vinyl chloride monomer (VCM) and to present control measures in the factories processing and producing polyvinyl chloride (PVC) resin. The conclusion remarks are as follows. Only two personal samples in the factory ("E") processing polyvinyl chloride resin were analysed to be 27.6 ppm and 12.6 ppm, respectively. But, these concentration exceed 1 ppm, Permissible Exposure Limits (PEL) of OSHA. So, worker's exposure to VCM at "E" factory should be reevaluated. In "A", "B" and "C" factory producing polyvinyl chloride resin, the average worker's exposures to VCM were 0.12 ppm, 0.86 ppm and 1.23 ppm, respectivery. Worker exposure to VCM at distillation and dry process was higer than other processes at "A" factory. The average exposure concentration of worker at polymerization process of "B" and "C" factory was 1.23 ppm, and 1.46 ppm respcetively. These concentration exceed 1 ppm, Permissible Exposure Limits of OSHA. Control room of "B" and "C" factory had 0.91 ppm and 0.65 ppm of worker's exposure concentration respectively. "A" factory was evaluated to be "acceptable", but "B" and "C" factories were evaluated to be "not acceptable", by the workplace exposure assessment program of AIHA. Process other than bagging and control room of "A" factory was evaluated to "not acceptable". Immediate correction measures for preventing workers from exposure to VCM should be performed in the factories or process that were evaluated to be "not acceptable". After these control measures are taken, worker exposure to VCM must be reevaluated through personal air monitoring. Control measures presented by this study are complete sealing of connecting pipe lines, flanging, packing, bolting and nutting. Periodic leak test for leak parts is also required. And positive pressure facility should be constructed at control room of "B" and "C" factory. Fresh air through cleaner such as HEPA filter should be supplied to control room. In addition to these control measures, periodic personal monitoring for evaluating worker exposure to VCM should be performed.

• Journal of Environmental Health Sciences
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• 제41권2호
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• pp.61-70
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• 2015

Objectives: The purpose of this research was to examine radon exposure in terms of the relationship between the living environment and indoor radon concentrations among vulnerable households. Methods: Nationwide, 1,129 subjects were selected using personal questionnaires for adequately understanding the living environment, installation of E-PERM radon gas detectors, and investigation of the structure of the housing. Results: The mean concentration of indoor radon for all subjects was $130.2Bq/m^3$ (GM=101.7), and a total of 438 subjects (38.8%) exceeded the recommended standards ($148Bq/m^3$) for public facilities by the Ministry of the Environment. By location, the highest concentrations ($164.3Bq/m^3$, GM=124.1) were seen in North Chungcheong Province. In the case of the Seoul/Gyeonggi Province metropolitan area, they showed $125.6Bq/m^3$ (GM=105.1) and $118.9Bq/m^3$ (GM=96.5), respectively. By type of housing, indoor radon concentrations in single-family housing were higher than in row/multi-family housing (p<0.01). Although indoor radon concentrations raised in accordance with year of construction (p<0.05), the difference between indoor radon concentrations in underground residences was not observed to be statistically significant (p=0.633). Conclusion: More studies are necessary in the future regarding the difference in indoor radon concentrations that may occur due to different of types of indoor construction, building materials, and the amount of building materials.

• The Korean Journal of Food And Nutrition
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• 제25권4호
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• pp.787-792
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• 2012

The objective of this study was to investigate the proper concentration of D-xylose which is expected to reduce the GI (Glycemic index) value of sucrose in the human body. When subjects took a sucrose mixture containing 5% and 10% D-xylose, the blood glucose levels were lowered by approximately 27.5% and 25.9%, respectively, compared to those of sucrose. The GI values of sucrose mixtures containing 5% and 10% D-xylose were 49.3 and 50.4, respectively. The reduction in GI value was not dependent on the D-xylose concentration, as the GI value of sucrose mixture containing 5% D-xylose (XyloSugar) was similar to that of sucrose mixture containing 10% D-xylose (XyloSugar10). D-xylose is not only more expensive but also less sweet than sucrose. So, low concentration of D-xylose has the advantage in the price and taste. It was determined that the proper concentration of D-xylose expected to reduce GI value of sucrose was 5% (w/w).

• Journal of Physiology & Pathology in Korean Medicine
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• 제28권4호
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• pp.390-395
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• 2014

Escherichia coli, Pseudomonas aeruginosa, Staphylococcus aureus, Listeria. monocytogenes and Bacillus cereus are pathogenic bacteria that should not be detected in cosmetics and foodstuffs. Therefore, we first investigated the antimicrobial activities of extracts of Scutellariae Radix(SR), Coptidis Rhizoma (CR) and salicylic acid(SA) in these pathogenic microorganisms. Although SA has been known to exhibit anti-inflammation and antimicrobial activity against pathogenic microorganisms, a high concentration of SA may cause serious side effects such as skin redness, skin burning, peeling or tissue damage. Hence, we focused on diminishing side effects followed by treatment of a high concentration of SA and investigated whether the combinations of SA with various concentrations(25-400 mg/mL), SR and CR with a concentration(100 mg/mL) which did not show antimicrobial activity against E. coli and P. aeruginosa exhibited meaningful antimicrobial effect against both strains. In our results, the combinations of SA with the lowest concentration(25 mg/mL), SR(100 mg/mL) and CR(100 mg/mL) exhibited significant antimicrobial activity against E.coli in comparison to SA alone(25 mg/mL) showing no antimicrobial activity. Moreover, the combinations of SA (100 mg/mL), SR and CR showed seven times higher antimicrobial activity against E. coli than SA alone(100 mg/mL) and exhibited a significant antimicrobial activity in comparison to ampicilin (p<0.05). The combinations of SA(100 mg/mL), SR and CR showed two times higher antimicrobial activity against P. aeruginosa than SA alone. Therefore, these results indicated that the combinations of SR, CR and SA with low concentration expressed the synergistic antimicrobial effect against E. coli and P. aeruginosa and showed great potential as an antimicrobial agent.

• Proceedings of the Korean Nuclear Society Conference
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• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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• pp.441-446
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• 1998

As for safety assessment of a radioactive waste disposal facility, radiation dose to inadvertent intruders is evaluated according to scenarios related to intruder's postulated activities at the disposal site after the end of Institutional Control Period(ICP). Simple trench and Below Ground Vault(BGV) are considered for this study as alternative disposal systems, and different scenarios are applied to each disposal type. The results show that 300 years of ICP is needed for simple trench and 100 years for BGV. Even for BGV, concentration of long-lived radioactive nuclides should be limited considering degradation of BGV after 300 years.