• Title/Summary/Keyword: Power Plant Park

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Application of Soil Stabilization Technique for Shoulder Construction in Sri Lanka (스리랑카 길어깨 적용을 위한 안정처리 재료의 적용성 평가 연구)

  • Park, Ki Soo;Park, Hee Mun
    • International Journal of Highway Engineering
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    • v.20 no.4
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    • pp.21-26
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    • 2018
  • PURPOSES : The objective of this study is to evaluate the application of soil stabilization method for soft shoulder construction in the iRoad Project of Sri Lanka. METHODS : Firstly, the quantitative analysis of soil strength improvement due to soil stabilization was done for soil samples collected from iRoad construction sites. Two types of soils were selected from iRoad Project sites and prepared for soil stabilization testing by the Road Development Authority. Secondly, the appropriate stabilizer was selected at given soil type based on test results. Two different stabilizers, ST-1 and ST-2, produced in Korea were used for estimating soil strength improvements. Finally, the optimum stabilizer content was determined for improving shoulder performance. The uniaxial compressive strength (UCS) test was conducted to evaluate the strength of stabilized soil samples in accordance with ASTM D 1633. The use of bottom ash as a stabilizer produced from power plant in Sri Lanka was also reviewed in this task. RESULTS : It is found from the UCS testing that a 3% use of soil stabilizer can improve the strength up to 2~5 times in stabilized soft shoulder soils with respect to unstabilized soils. It is also observed from UCS testing that the ST-1 shows high strength improvement in 3% of stabilizer content but the strength improvement rate with increase of stabilizer content is relatively low compared with ST-2. The ST-2 shows a low UCS value at 3% of content but the UCS values increase significantly with increase of stabilizer content. When using the ST-2 as stabilizing agent, the 5% is recommended as minimum content based on UCS testing results. Based on the testing results for bottom ash replacement, the stabilized sample with bottom ash shows the low strength value. CONCLUSIONS : This paper is intended to check the feasibility for use the soil stabilization technique for shoulder construction in Sri Lanka. The use of soil stabilizer enables to improve the durability and strength in soft shoulder materials. When applying the bottom ash as a soil stabilizer, various testings should be conducted to satisfy the specification criteria.

Fatigue Behavior of STS316L Weldments and Degradation Characteristic Evaluation by Ultrasonic Test (STS316L 용접부의 피로거동 및 초음파시험에 의한 열화특성 평가)

  • Nam, Ki-Woo;Park, So-Soon;Ahn, Seok-Hwan;Do, Jae-Yoon;Park, In-Duck
    • Journal of the Korean Society for Nondestructive Testing
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    • v.23 no.2
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    • pp.156-164
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    • 2003
  • STS316L had been used as the structural material for energy environmental facilities, because austenite stainless steels like 316L have superior mechanical properties of which toughness, ductility, corrosion resistant and etc. However, those welded structures are receiving severe damage due to increasing of the aged degradation. Most studies until now have been carried out against fatigue behaviors of weldments, and were not well studied on nondestructive evaluation methods. In this study, the fatigue crack propagation behavior of STS316L weldment usually used for vessels of the nuclear power plant was investigated. Also, the degradation characteristics of 316L stainless steel weldments were evaluated by the ultrasonic parameter such as ultrasonic velocity, attenuation factor and time-frequency analysis. The results of this study can be used as a basic data for the prediction of the fatigue crack life of weldments structures without disjointing or stopping service of structures in service.

Carbon dioxide absorption characteristics according to amine mixtures with different order (급수가 다른 아민 혼합에 따른 이산화탄소 흡수 특성)

  • Choi, Soo-Hyun;You, Jong-Kyun;Park, Ki-Tae;Baek, Il-Hyun;Park, So-Jin
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.14 no.9
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    • pp.4635-4642
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    • 2013
  • The advanced absorbent that used amine mixture with different order were developed to separate carbon dioxide emitted from fossil fuel power plant. The carbon dioxide absorption capacity for mixtures with different amine(primary, secondary and tertiary) were investigated according to $CO_2$ partial pressure. The carbon dioxide absorption capacity at the same pressure is ordered as 3DMA1P 30wt%>3DMA1P 27wt%+MEA 3wt%>3DMA1P 27wt%+DEA 3wt%. The result indicates that mixing tertiary amine with primary amine yields more efficient carbon dioxide absorbent than mixing tertiary with secondary amine does. Finally, the predicted semi-empirical gas-liquid equilibrium model fitted with experimental results.

Development of the Pilot System for Radioactive Laundry Waste Treatment Using UV Photo-Oxidation Process and Reverse Osmosis Membrane

  • Park, Se-Moon;Park, Jong-Kil;Kim, Jong-Bin;Shin, Sang-Woon;Lee, Myung-Chan
    • Nuclear Engineering and Technology
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    • v.31 no.5
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    • pp.506-511
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    • 1999
  • The pilot system for radioactive liquid laundry waste was developed with treatment capacity, 1ton/hr and set up in the Yong Kwang unit #4. The system is composed of tank module, RO systems and a UV/$H_2O$$_2$photo-oxidation unit. The RO system consists of the BW unit (low-pressure RO for brackish water desalination) and the SW unit (high-pressure RO for seawater desalination). The BW unit possesses 4 RO membranes and it can reduce the feed water volume down to 1/10. This concentrated feed water can be reduced again up to 1/10 in its volume in the SW unit composed of 4 RO membranes. The UV/$H_2O$$_2$ photo-oxidation process unit was used for the detergent degradation. The operation of the pilot system was carried out and verified in its capability through the continuous operation and concentration operation using the actual liquid waste from the power plant. The design criteria and data for industrialization were yielded. The efficiency of the UV/$H_2O$$_2$ photo-oxidation process and the optimum operational procedure were evaluated. The decontamination factors for radioactive cobalt and cesium were measured. This on-site test showed the experimental result in the DF$\geq$300 and volume reduction factor$\geq$100.

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Preliminary Design of the Forced Gas Drying System for Spent Nuclear Fuel Dry Storage (사용후핵연료 건식저장을 위한 기체강제순환 건조장치 예비설계)

  • Chae, Gyung-sun;Shin, Kyung-wook;Park, Byeong-mok;Han, Jae-hyun;Lee, Geon-hui;Park, Jae-seok
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.4
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    • pp.403-409
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    • 2017
  • For dry storage of the spent nuclear fuel (SNF) stored in the storage pool of a nuclear power plant, essentially all moisture must be removed to prevent corrosion of the assembly and canister internals and/or degradation of fuel cladding integrity after SNF canister loading operation. R&D work is now in progress on a forced gas drying system that can be used to remove residual water in canisters. In this work, preliminary design is performed to manufacture the forced gas drying system. This process includes a case study of dry methods for canister moisture removal, relative codes and standards, confirmation of adequate dryness, needs analysis at plant sites, and characteristics of SNF stored in pools. Through this preliminary design work, we obtained a conceptual flow diagram and preliminary P&ID of the forced gas drying system. The results of this study can be used to determine details of the design to manufacture the forced gas drying system.

Characteristics of Coal Devolatilization and Spontaneous Combustion at Low Temperatures (저온영역에서 석탄의 탈휘발 및 자연발화 특성 연구)

  • Sung Min Yoon;Seok Hyeong Lee;Tae Hwi An;Myung Won Seo;Sang Won Lee;Dae Sung Kim;Tae-Young Mun;Sung Jin Park;Sang Jun Yoon;Ji Hong Moon;Jae Goo Lee;Jong Hoon Joo;Ho Won Ra
    • Clean Technology
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    • v.29 no.4
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    • pp.288-296
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    • 2023
  • Coal is abundantly available compared to other energy sources and is used as a versatile energy resource worldwide. To address the environmental issues stemming from conventional coal utilization, efforts are underway to develop clean coal utilization technologies, with IGCC technology being a notable example. In IGCC plants, coal is subjected to a CMD process where both drying and pulverization are achieved by supplying hot air. However, if the temperature of the supplied hot air is excessively high, it can lead to devolatilization and spontaneous combustion, thereby compromising the stable operation of the CMD process. This study aimed to measure the devolatilization and spontaneous combustion temperatures of different types of bituminous coal, and to explore their correlations with the characteristics of the coals. Six coal types exhibited devolatilization between 350 and 400 ℃, while three coal types showed devolatilization at temperatures exceeding 400 ℃. Spontaneous combustion ℃curred in one coal type below 100 ℃, six coal types between 100 and 150 ℃, and two coal types above 150 ℃. The measured initiation temperatures were compared with the coal characteristics including the oxygen, moisture, Fe2O3, and CaO content, the H/C ratio, and the O/C ratio to establish correlations. Regression analysis was used to calculate the regression coefficients and determination coefficients for each ignition temperature. It was found that 52.44% of the FC/VM data significantly influenced the volatile matter ignition temperature, and 59.10% of the Fe2O3 data significantly affected the spontaneous combustionignition temperature.

Experimental Study of Chemical Effects on Head Loss across Containment Sump Strainer under Post-LOCA Environment (LOCA이후 원자로건물집수조 여과기의 수두손실에 대한 화학적 영향의 실험연구)

  • Ku, Hee-Kwan;Jung, Bum-Young;Hong, Kwang;Jung, Eun-Sun;Jeong, Hyun-Jun;Park, Byung-Gi;Rhee, In-Hyoung;Park, Jong-Woon
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.10 no.12
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    • pp.3748-3754
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    • 2009
  • An integral head loss test in a test apparatus was conducted to simulate chemical effects on a head loss across a strainer in a pressurized water reactor (PWR) containment water pool after a loss of coolant accident (LOCA). The test was conducted during 30 days in the condition of a short spray, a long spray, and no materials with chemical effects. The result exhibited that the head loss was affected on amounts of the exposed materials according to spray conditions. XRD analysis of the collected precipitates showed that the precipitates were phosphate compounds. Comparison of the head loss with dissolved species concentration showed that high increase rate of the head loss resulted from the corrosion of aluminum and zinc but slow increase rate of the head loss resulted from the precipitates induced by Si, Mg, and Ca from leaching reaction at NUKON and concrete after passivation of metal specimens.

Chemical Effects on Head Loss across Containment Sump Strainer under Post-LOCA Environment (LOCA이후 환경에서 원자로건물집수조 여과기의 수두손실에 대한 화학적 영향)

  • Ku, Hee-Kwon;Jung, Bum-Young;Hong, Kwang;Jeong, Eun-Sun;Jung, Hyun-Jun;Park, Byung-Gi;Rhee, In-Hyoung;Park, Jong-Woon
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.10 no.11
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    • pp.3260-3268
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    • 2009
  • A test apparatus has been fabricated to simulate chemical effect on head loss through a strainer in a pressurized water reactor (PWR) containment water pool after a loss of coolant accident (LOCA). Tests were conducted under condition of same ratio of strainer surface area to water volume between the test appratus and the containment sump. A series of tests have been performed to investigate the effects of spray, existence of calcium-silicate with tri-sodium phosphate (TSP), and composition of materials. The results showed that head loss across the chemical bed with even a small amount of calcium-silicate insulation instantaneously increased as soon as TSP was added to the test solution. Also, the head loss across the test screen is strongly affected by spray duration and is increased rapidly at the early stage, because of high dissolution and precipitation of aluminum and zinc. After passivation of aluminum and zinc by corrosion, the head loss increase is much slowed down and is mainly induced by materials such as calcium, silicon, and magnesium leached from NUKONTM and concrete. Furthermore, it is newly found that the spay buffer agent, tri-sodium phosphate, to form protective coating on the aluminum surface and reduce aluminum leaching is not effective for a large amount of aluminum and a long spray.

Evaluation of nitrogen oxide removal characteristics using TiO2 (TiO2를 이용한 질소산화물 제거 특성 평가)

  • Park, Jun-Gu;Lim, Hee-Ah;Park, Young-Koo
    • Journal of the Korean Applied Science and Technology
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    • v.36 no.2
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    • pp.668-675
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    • 2019
  • Fine dust in air pollutants is recognized as one of the most serious social environmental problems. Most of the NOx is generated in a combustion process such as that of a coal-fired power plant, and therefore efficient elimination of the NOx from the coal-fired power plants is needed. This study investigates the removal efficiency of using $TiO_2$, a photocatalyst, to remove NOx by Selective Catalytic Reduction (SCR). To evaluate the NOx removal efficiency, $TiO_2$ catalyst and phosphate binder were mixed on the surface of the $Al_2O_3$ substrate with the exothermic agent, and the substrate was heat-treated. The NOx removal efficiency of the catalysts was evaluated according to the temperature, and XRD, SEM, TG-DTA and BET analyzes were performed to investigate the physicochemical properties of the catalysts. NOx removal efficiency was 58.7%~65.9% at 20min, 63.7~66.0% at 30min with temperature change according to time($250^{\circ}C{\sim}500^{\circ}C$). The $TiO_2$ used in the SCR for NOx removal is judged to have the most efficient removal efficiency at $300^{\circ}C$.

Current Status of the Radioactive Waste Management Program in Korea

  • Park, H-S;Hwang, Y-S;Kang, C-H
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.02a
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    • pp.140-142
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    • 2004
  • Since the April of 1978, Korea has strongly relied on the nuclear energy for electricity generation. As of today, eighteen nuclear power plants are in operation and ten are to be inaugurated by 2015. The installed nuclear capacity is 15, 716 MW as of the end of 2002, representing 29.3% of the nation's total installed capacity. The nuclear share in electricity remains around 38.9 at the end of 2002, reaching at the level of 119 billion kWh's. New power reactors, KSNP's (Korea Standard Nuclear Power Plant) are fully based on the domestic technologies. More advanced reactors such as KNGR (Korea Next Generation Reactor) will be commercialized soon. Even though the front end nuclear cycle enjoys one of the best positions in the world, there have been some chronical problems in the back end fuel cycle. That's the one of the reason why we need more active R&D programs in Korea and active international and regional cooperation in this area. The everlasting NIMBY problem hinders the implementation of the nation's radioactive waste management program. We expect that the storage capacity for the LILW(Low and Intermediate Level radioactive Waste) will be dried out soon. The situation for the spent fuel storage is also not so favorable too. The storage pools for spent fuel are being filled rapidly so that in 2008, some AR pools cannot accommodate any more new spent nuclear fuels. The Korean Government in strong association with utilities and national academic and R&D institutes have tried its best effort to secure the site for a LILW repository and a AFR site. Finally, one local community, Buan in Jeonbook Province, submitted the petition for the site. At the end of the last July, the Government announced that the Wido, a small island in Buan, is suitable for the national complex site. The special force team headed by Dr IS Chang, president of KAERI teamed with Government officials and many prominent scholars and journalists agreed that by the evidences from the preliminary site investigation, they could not find any reason for rejecting the local community's offer.

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