• 제목/요약/키워드: Won Bang

검색결과 1,169건 처리시간 0.028초

Effect of Starvation on Kidney Melano-macrophage Centre in Sub-adult Rock Bream, Oplegnathus fasciatus (Temminck and Schlegel)

  • Seol, Dong-Won;Hur, Jun-Wook;Kim, Dong-Soo;Nam, Yoon-Kwon;Bang, In-Chul;Park, In-Seok
    • Fisheries and Aquatic Sciences
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    • 제12권1호
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    • pp.49-53
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    • 2009
  • We conducted a histological analysis to investigate the influence of nutritional changes on melano-macrophages (MMs) accumulation in the kidney of sub-adult rock bream (Oplegnathus fasciatus). Four experimental groups were established (initial control, control, fed and starved), and fed commercial feed amounting to 1-3% of their body weight for 2 weeks prior to initiation of experiments. Kidney MMs with dark brown pigment were randomly observed in the kidneys of starved fish, increasing rapidly after 4 weeks, while deposition levels remained low throughout the experiment in the control and fed groups. These results suggest that catabolic tissue breakdown is a major factor contributing to the formation of pigments within MMs. Results also suggest that the degree of MMs deposition in the kidney can be used as alternative indicators in identifying starvation in wild and cultured rock bream.

레일리 감쇄 채널에서 차분 문턱간 검정을 쓴 M진 주파수 편이 변조 신호검파 (Detection of M-FSK Signals with Difference Threshold Test in Rayleigh Fading Channels)

  • 김홍직;강현구;김선용;권형문;방만원;송익호
    • 한국통신학회논문지
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    • 제30권10C호
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    • pp.999-1006
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    • 2005
  • 차분 문턱값 검정에서는 (difference threshold test: DTT) 에너지 검파기 출력들 가운데 가장 큰 출력과 둘째로 큰 출력의 차이가 문턱값을 넘지 않으면 심벌을 잃음으로 본다. 변조 크기와 다양성 차수가 유한하면, M진 주파수 편이 신호를 검파할 때 차분 문턱값 검정이 비율 문턱값 검정보다 (ratio threshold test: RTT) 성능이 좋다는 것을 보이고, 변조 크기와 다양성 차수가 무한히 클 때의 점근 성능을 알아본다. 차분 문턱값 검정을 쓰거나 비율 문턱값 검정을 쓰거나 잘못 없이 통신할 수 있는 가장 작은 신호대잡음비는 같다는 것을 보인다.

On the Multiuser Diversity in SIMO Interfering Multiple Access Channels: Distributed User Scheduling Framework

  • Shin, Won-Yong;Park, Dohyung;Jung, Bang Chul
    • Journal of Communications and Networks
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    • 제17권3호
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    • pp.267-274
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    • 2015
  • Due to the difficulty of coordination in the cellular uplink, it is a practical challenge how to achieve the optimal throughput scaling with distributed scheduling. In this paper, we propose a distributed and opportunistic user scheduling (DOUS) that achieves the optimal throughput scaling in a single-input multiple-output interfering multiple-access channel, i.e., a multi-cell uplink network, with M antennas at each base station (BS) and N users in a cell. In a distributed fashion, each BS adopts M random receive beamforming vectors and then selects M users such that both sufficiently large desired signal power and sufficiently small generating interference are guaranteed. As a main result, it is proved that full multiuser diversity gain can be achieved in each cell when a sufficiently large number of users exist. Numerical evaluation confirms that in a practical setting of the multi-cell network, the proposed DOUS outperforms the existing distributed user scheduling algorithms in terms of sum-rate.

초전도 전력케이블의 1선 지락고장 특성 해석에 관한 연구 (A Study on the Single Line-to-Ground Fault Analysis of HTS Power Cable)

  • 제향호;방종현;김재호;심기덕;조전욱;장현만;이수길;박민원;유인근
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2006년도 제37회 하계학술대회 논문집 B
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    • pp.1259-1260
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    • 2006
  • High temperature superconducting(HTS) power cable is expected to be used for power transmission lines supplying electric power for densely populated cities in the near future. Commercializing of HTS power cable is coming. Simulation is required for safety before install of HTS power cable, a fabrication model used at the power system simulation. In this paper, we shows a single line-to ground fault analysis in the grid system which has a 100m length HTS power cable. The authors developed a single line-to-ground fault current calculation method which is considering the shield layer of HTS power cable. In the calculation, the T type equivalent circuit is used to derive the mutual inductance of the HTS power cable.

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Loss of Coolant Accident Analysis During Shutdown Operation of YGN Units 3/4

  • Bang, Young-Seok;Kim, Kap;Seul, Kwang-Won;Kim, Hho-Jung
    • Nuclear Engineering and Technology
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    • 제31권1호
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    • pp.17-28
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    • 1999
  • A thermal-hydraulic analysis is conducted on the loss-of-coolant-accident (LOCA) during shutdown operation of YGN Units 3/4. Based on the review of plant-specific characteristics of YGN Units 3/4 in design and operation, a set of analysis cases is determined, and predicted by the RELAP5/MOD3.2 code during LOCA in the hot-standby mode. The evaluated thermal-hydraulic phenomena are blowdown, break flow, inventory distribution, natural circulation, and core thermal response. The difference in thermal-hydraulic behavior of LOCA at shutolown condition from that of LOCA at full power is identified as depressurization rate, the delay in peak natural circulation timing and the loop seal clearing (LSC) timing. In addition, the effect of high pressure safety injection (HPSI) on plant response is also evaluated. The break spectrum analysis shows that the critical break size can be between 1% to 2% of cold leg area, and that the available operator action time for the Sl actuation and the margin in the peak clad temperature (PCT) could be reduced when considering uncertainties of the present RELAP5 calculation.

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Containment Closure Time Following the Loss of Shutdown Cooling Event of YGN Units 3&4

  • Seul, Kwang-Won;Bang, Young-Seok;Kim, Hho-Jung
    • Nuclear Engineering and Technology
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    • 제31권1호
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    • pp.68-79
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    • 1999
  • The YGN Units 3&4 plant conditions during shutdown operation were reviewed to identify the possible event scenarios following the loss of shutdown cooling (SDC) event. For the five cases of typical reactor coolant system (RCS) configurations under the worst event sequence, such as unavailable secondary cooling and no RCS inventory makeup, the thermal hydraulic analyses were performed using the RELAP5/MOD3.2 code to investigate the plant behavior following the event. The thermal hydraulic analyses include the estimation of time to boil, time to core uncovery, and time to core heat up to determine the containment closure time to prevent the uncontrolled release of fission products to atmosphere. The result indicates that the containment closure is recommended to be achieved within 42 minutes after the loss of SDC for the steam generator (SG) inlet plenum manway open case or the large cold leg open case under the worst event sequence. The containment closure time is significantly dependent on the elevation and size of the opening and the SG secondary water level condition. It is also found that the containment closure needs to be initiated before the boiling time to ensure the survivability of the workers in the containment. These results will provide useful information to operators to cope with the loss of SDC event.

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Phytol, SSADH Inhibitory Diterpenoid of Lactuca sativa

  • Bang, Myun-Ho;Choi, Soo-Young;Jang, Tae-O;Kim, Sang-Kook;Kwon, Oh-Shin;Kang, Tae-Cheon;Won, Moo-Ho;Park, Jin-Seu;Baek, Nam-In
    • Archives of Pharmacal Research
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    • 제25권5호
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    • pp.643-646
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    • 2002
  • The succinic semialdehyde dehydrogenase (SSADH) inhibitory component was isolated from the EtOAc fraction of Lactuca sativa through repeated column chromatography; then, it was identified as phytol, a diterpenoid, based on the interpretation of several spectral data. Incubation of SSADH with the phytol results in a time-dependent loss of enzymatic activity, suggesting that enzyme modification is irreversible. The inactivation followed pseudo-first-order kinetics with the second-rate order constant of $6.15{\times}10^{-2}mM^{-1}min^{-1}.$ Complete protection from inactivation was afforded by the coenzyme $NAD^{+}$, whereas substrate succinic semialdehyde failed to prevent the inactivation of the enzyme; therefore, it seems likely that phytol covalently binds at or near the active site of the enzyme. It is postulated that the phytol is able to elevate the neurotransmitter GABA levels in central nervous system through its inhibitory action on one of the GABA degradative enzymes, SSADH.

MODELING THE HYDRAULIC CHARACTERISTICS OF A FRACTURED ROCK MASS WITH CORRELATED FRACTURE LENGTH AND APERTURE: APPLICATION IN THE UNDERGROUND RESEARCH TUNNEL AT KAERI

  • Bang, Sang-Hyuk;Jeon, Seok-Won;Kwon, Sang-Ki
    • Nuclear Engineering and Technology
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    • 제44권6호
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    • pp.639-652
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    • 2012
  • A three-dimensional discrete fracture network model was developed in order to simulate the hydraulic characteristics of a granitic rock mass at Korea Atomic Energy Research Institute (KAERI) Underground Research Tunnel (KURT). The model used a three-dimensional discrete fracture network (DFN), assuming a correlation between the length and aperture of the fractures, and a trapezoid flow path in the fractures. These assumptions that previous studies have not considered could make the developed model more practical and reasonable. The geologic and hydraulic data of the fractures were obtained in the rock mass at the KURT. Then, these data were applied to the developed fracture discrete network model. The model was applied in estimating the representative elementary volume (REV), the equivalent hydraulic conductivity tensors, and the amount of groundwater inflow into the tunnel. The developed discrete fracture network model can determine the REV size for the rock mass with respect to the hydraulic behavior and estimate the groundwater flow into the tunnel at the KURT. Therefore, the assumptions that the fracture length is correlated to the fracture aperture and the flow in a fracture occurs in a trapezoid shape appear to be effective in the DFN analysis used to estimate the hydraulic behavior of the fractured rock mass.

ANALYSIS OF UNCERTAINTY QUANTIFICATION METHOD BY COMPARING MONTE-CARLO METHOD AND WILKS' FORMULA

  • Lee, Seung Wook;Chung, Bub Dong;Bang, Young-Seok;Bae, Sung Won
    • Nuclear Engineering and Technology
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    • 제46권4호
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    • pp.481-488
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    • 2014
  • An analysis of the uncertainty quantification related to LBLOCA using the Monte-Carlo calculation has been performed and compared with the tolerance level determined by the Wilks' formula. The uncertainty range and distribution of each input parameter associated with the LOCA phenomena were determined based on previous PIRT results and documentation during the BEMUSE project. Calulations were conducted on 3,500 cases within a 2-week CPU time on a 14-PC cluster system. The Monte-Carlo exercise shows that the 95% upper limit PCT value can be obtained well, with a 95% confidence level using the Wilks' formula, although we have to endure a 5% risk of PCT under-prediction. The results also show that the statistical fluctuation of the limit value using Wilks' first-order is as large as the uncertainty value itself. It is therefore desirable to increase the order of the Wilks' formula to be higher than the second-order to estimate the reliable safety margin of the design features. It is also shown that, with its ever increasing computational capability, the Monte-Carlo method is accessible for a nuclear power plant safety analysis within a realistic time frame.

Simulation of Multiple Steam Generator Tube Rupture (SGTR) Event Scenario

  • Seul Kwang Won;Bang Young Seok;Kim In Goo;Yonomoto Taisuke;Anoda Yoshinari
    • Nuclear Engineering and Technology
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    • 제35권3호
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    • pp.179-190
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    • 2003
  • The multiple steam generator tube rupture (SGTR) event scenario with available safety systems was experimentally and analytically evaluated. The experiment was conducted on the large scaled test facility to simulate the multiple SGTR event and investigate the effectiveness of operator actions. As a result, it indicated that the opening of pressurizer power operated relief valve was significantly effective in quickly terminating the primary-to-secondary break flow even for the 6.5 tubes rupture. In the analysis, the recent version of RELAP5 code was assessed with the test data. It indicated that the calculations agreed well with the measured data and that the plant responses such as the water level and relief valve cycling in the damaged steam generator were reasonably predicted. Finally, sensitivity study on the number of ruptured tubes up to 10 tubes was performed to investigate the coolant release into atmosphere. It indicated that the integrated steam mass released was not significantly varied with the number of ruptured tubes although the damaged steam generator was overfilled for more than 3 tubes rupture. These findings are expected to provide useful information in understanding and evaluating the plant ability to mitigate the consequence of multiple SGTR event.