• Title/Summary/Keyword: surface code

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Speciation and Ecological Risk Assessment of Trace Metals in Surface Sediments of the Masan Bay (마산만 표층퇴적물에서 미량금속의 화학적 존재형태 및 생태계 위해도 평가)

  • Sun, Chul-In;Lee, Young-Ju;An, Jung-Hyun;Lee, Yong-Woo
    • The Sea:JOURNAL OF THE KOREAN SOCIETY OF OCEANOGRAPHY
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    • v.19 no.2
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    • pp.155-163
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    • 2014
  • Total concentration and chemical speciation of trace metals (Cu, Pb, Zn, Cd, and Ni) were determined to evaluate pollution level and potential ecological risk in surface sediments of the Masan Bay. The results showed that the trace metal concentrations, except for Ni, were high in the inner Masan Bay. Based on the chemical speciation of metals in sediments, the percentage of total concentrations of Cd and Pb in non-residual fraction was 92% and 88%, respectively, indicating that these metals originated mainly from anthropogenic sources. However, Ni (70%) was dominant in residual fraction. Pollution load index (PLI) and ecological risk index (ERI) values in the inner bay indicate the presence of anthropogenic pollution and considerable-moderate ecological risk, respectively. Ecological index (Ei) value for Cd was high at most stations in the Masan Bay, and Cd content was the highest in acid soluble fraction, which presents the highest ecological risk. The results obtained in this study indicate that Cd presents a high potential ecological risk to benthic biota in the Masan Bay.

Residual Radioactivity Investigation & Radiological Assessment for Self-disposal of Concrete Waste in Nuclear Fuel Processing Facility (콘크리트 폐기물의 자체처분을 위한 잔류방사능 조사 및 피폭선량평가)

  • Seol, Jeung-Gun;Ryu, Jae-Bong;Cho, Suk-Ju;Yoo, Sung-Hyun;Song, Jung-Ho;Baek, Hoon;Kim, Seong-Hwan;Shin, Jin-Seong;Park, Hyun-Kyoun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.2
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    • pp.91-101
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    • 2007
  • In this study, domestic regulatory requirement was investigated for self-disposal of concrete waste from nuclear fuel processing facility. And after self-disposal as landfill or recycling/reuse, the exposure dose was evaluated by RESRAD Ver. 6.3 and RESRAD BUILD Ver.3.3 computing code for radiological assessments of the general public. Derived clearance level by the result of assessments for the exposure dose of the general public is 0.1071Bq/g (3.5% enriched uranium) for landfill and $0.05515Bq/cm^2$ (5% enriched uranium) for recycling/reuse respectively. Also, residual radioactivity of concrete waste after decontamination was investigated in this study. The result of surface activity is $0.01Bq/cm^2\;for\;{\alpha}-emitter$ and the result of radionuclide analysis for taken concrete samples from surface of concrete waste is 0.0297Bq/g for concentration of $^{238}U$, below 2w/o for enrichment of $^{235}U$ and 0.0089Bq/g for artificial contamination of $^{238}U$ respectively. Therefore, radiological hazard of concrete waste by self-disposal as landfill and recycling/reuse is below clearance level to comply with clearance criterion provided for Notice No.2001-30 of the MOST and Korea Atomic Energy Act.

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Alteration of the Stability in Training Ship Pusan 403 (실습선 부산403호의 복원성 변화)

  • KIM Sam-Kon;KIM Jong-Hwa;CHOE Jong-Hwa;KIM Yeong-Sik
    • Korean Journal of Fisheries and Aquatic Sciences
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    • v.18 no.2
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    • pp.94-100
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    • 1985
  • M/S Pusan 403(GT 243, 1000ps) was originally built as a research vessel on skipjack pole and line fishing in 1972. She had begun to serve as a fishing training ship of National Fisheries University of Pusan from 1974, since the interior structure has been remodelled and some weight articles have been removed, her stability is in doubt. The authors carried out an inclining experiment by using two pendulums at fore and aft with two weights on both sides. Each value obtained was compared with the IMO safety code for fishing vessels and safety regulation for fishing vessels of Korea. 1. The GZ value, being 0.207 m under light ship condition and 0.325 m under departure condition with full load, can be assumed as no impediment on her stability, 2. Under the light ship condition, GM decreased by 0.046 m and KG increased by 0.141 m, compared with the values determined at the time of official sea trial. Therefore, no impediment on the stability exists. 3. The GM decreased by 0.163 m and the KG increased by 0.173 m, compared with the values determined at the time of official sea trial. In no consideration of the free surface effects of liquid in the oil and fresh water tanks, no impediment on the stability exists. But, in consideration of the free surface effect, it may be regarded that some impediment exists.

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The Detection of Heat Emission to Solar Cell using UAV-based Thermal Infrared Sensor (UAV 기반 열적외선 센서를 이용한 태양광 셀의 발열 검출)

  • Lee, Geun Sang;Lee, Jong Jo
    • Journal of Korean Society for Geospatial Information Science
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    • v.25 no.1
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    • pp.71-78
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    • 2017
  • Many studies have been implemented to manage solar plant being supplied widely in recent years. This study analyzed heat emission of solar cell using unmanned aerial vehicle(UAV)-based thermal infrared sensor, and major conclusions are as belows. Firstly, orthomosaic image and digital surface model(DSM) data were acquired using UAV-based RGB sensor, and solar light module layer necessary to analyze the heat emission of solar cell was constructed by these data. Also as a result of horizontal error into validation points using virtual reference service(VRS) survey for evaluating the location accuracy of solar light module layer, higher location accuracy could be acquired like standard error of $dx={\pm}2.4cm$ and $dy={\pm}3.2cm$. And this study installed rubber patch to test the heat emission of solar cell and could analyzed efficiently the location of rubber patch being emitted heat using UAV-based thermal infrared sensor. Also standard error showd as ${\pm}3.5%$ in analysis between calculated cell ratio by rubber patch and analyzed cell ratio by UAV-based thermal infrared sensor. Therefore, it could be efficiently analyzed to heat emission of solar cell using UAV-based thermal infrared sensor. Also efficient maintenance of solar plant could be possible through extracting the code of solar light module being emitted of heat automatically.

Beta Dosimetry for Applying $^{166}Ho$-chitosan Complex to Cystic Brain Tumor Treatment : Monte Carlo Simulations Using a Spherical Model ($^{166}Ho$-chitosan 복합체를 이용한 낭성뇌종양 치료를 위한 베타선의 흡수선량 평가 : 구형 모델을 이용한 Monte Cairo 모사계산)

  • Kim, Eun-Hee;Rhee, Chang-Hun;Lim, Sang-Moo;Park, Kyung-Bae
    • The Korean Journal of Nuclear Medicine
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    • v.31 no.4
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    • pp.433-439
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    • 1997
  • $^{166}Ho$-chitosan complex, or $^{166}Ho$-CHICO, is a candidate pharmaceutical for intracavitary radiation therapy of cystic brain tumors because of the desirable nuclear characteristics of $^{166}Ho$ for therapeutic use and the suitable biological and chemical characteristics of chitosan, not to mention its ready producibility The amount of $^{166}Ho$-CHICO to be administered to obtain the goal therapeutic effect can be suggested by predicting the dose to the cyst wall for a varying pharmaceutical dose. When $^{166}Ho$-CHICO is infused into the cyst, the major part of the energy delivery by beta particles emitted from $^{166}Ho$ occurs in the cyst wall within 4mm in depth from the cyst wall surface. Also, realizing the attachment of $^{166}Ho$-CHICO to the cyst wall surface would change the predictions of dose to the cyst wall.

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Development of the Phased Array Ultrasonic Testing Technique for Nuclear Power Plant's Small Bore Piping Socket Weld (원전 소구경 배관 소켓용접부 위상배열 초음파검사 기술 개발)

  • Yoon, Byung-Sik;Kim, Yong-Sik;Lee, Jeong-Seok
    • Journal of the Korean Society for Nondestructive Testing
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    • v.33 no.4
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    • pp.368-375
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    • 2013
  • Failure of small bore piping welds is a recurring problem at nuclear power plants. And the socket weld cracking in small bore piping has caused unplanned plant shutdowns for repair and high economic impact on the plants. Consequently, early crack detection, including the detection of manufacturing defects, is of the utmost importance. Until now, the surface inspection methods has been applied according to ASME Section XI requirements. But the ultrasonic inspection as a volumetric method is also applying to enforce the inspection requirement. However, the conventional manual ultrasonic inspection techniques are used to detect service induced fatigue cracks. And there was uncertainty on manual ultrasonic inspection because of limited access to the welds and difficulties with contact between the ultrasonic probe and the OD(outer diameter) surface of small bore piping. In this study, phased array ultrasonic inspection technique is applied to increase inspection speed and reliability. To achieve this object, the 3.5 MHz phased array ultrasonic transducer are designed and fabricated. The manually encoded scanner was also developed to enhance contact conditions and maintain constant signal quality. Additionally inspection system is configured and inspection procedure is developed.

Evaluation of Residual Radiation and Radioactivity Level of TRIGA Mark-II, III Research Reactor Facilities for Safe Decommissioning (TRIGA Mark-II, III 연구로 시절의 폐로를 위한 시설의 잔류 방사선/능 평가)

  • Lee, B.J.;Chang, S.Y.;Park, S.K.;Jung, W.S.;Jung, K.J.
    • Journal of Radiation Protection and Research
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    • v.24 no.2
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    • pp.109-120
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    • 1999
  • Residual radiation and radioactivity level in TRIGA Mark-II, III research reactors and facilities at the KAERI Seoul site, which are to be decommissioned, have been measured, analyzed and evaluated to know the current status of radiation and radioactivity level and to establish and to provide the technical requirements for the safe decommissioning of the facilities which shall be applied in minimizing the radiation exposure for workers and in preventing the release of the radioactive materials to the environment. Radiation dose rate and surface radioactivity contamination level on the experimental equipments, floors, walls of the facilities, and the surface of the activated materials within the reactor pool structure were measured and evaluated. Radioactivity and radionuclides in the pool and cooling water were also analyzed. In case of the activated reactor pool structures which are very difficult to measure the radiation and radioactivity level, a computer code Fispin was additionally used for estimation of the residual radioactivity and radionuclides. The radiation and radioactivity data obtained in this study were effectively used as basic data for decontamination and dismantling plan for safe decommissioning of TRIGA Mark-II, III facilities.

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Dosimetry and Medical Internal Radiation Dose of Re-188-DTPA for Endovascular Balloon Brachytherapy Against Restenosis after Coronary Angioplasty (혈관성형술 후 재협착 방지 치료에 사용하기 위한 원통형 풍선 Re-188-DTPA의 선량 분포와 내부피폭 선량)

  • Lee, Jin;Lee, Dong-Soo;Shin, Seung-Ae;Jeong, Jae-Min;Chung, June-Key;Lee, Myung-Chul
    • The Korean Journal of Nuclear Medicine
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    • v.33 no.2
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    • pp.163-171
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    • 1999
  • Purpose: Liquid beta emitter filled in angioplasty balloon could be used to perform endovascular balloon brachytherapy to prevent coronary artery restenosis. We investigated the dosimetry for Re-188-DTPA liquid-filled balloon and medical internal radiation dosimetry in case of balloon leakage. Materials and Methods: We estimated radiation dose from an angioplasty balloon (20 mm length, 3 mm diameter cylinder) to the adjacent vessel wall using Monte Carlo EGS4 code. We obtained time-activity curves of kidneys in normal dog and calculated $T_{max},\;T_{1/2}$. Using MIRDOSE3 program, we estimated absorbed doses to the major organs (kidneys, bladder) and the whole body when we assumed that balloon leaked all the isotope contained. Results: The radiation dose was 17.5 Gy at the balloon surface when we applied 3,700 MBq/ml of Re-188 for 100 seconds, Fifty percent of the energy deposited within 1 mm from the balloon surface. The estimated internal dose to the whole body was 0.005 mGy/MBq and 18.5 mGy for the spillage of 3,700 MBq of Re-188. Conclusion: We suggest that Re-188-DTPA can be used for endovascular balloon brachytherapy to inhibit coronary artery restenosis after angioplasty with tolerable whole body radiation dose in case of balloon rupture.

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Numerical Analysis of Heat Transfer Characteristics of Ribbed Channels with Different Film Cooling Hole Position (필름 냉각을 위한 리브드 채널의 홀 위치에 따른 열전달 특성 수치 해석)

  • Park, Jee Min;Moon, Joo Hyun;Lee, Hyung Ju;Lee, Seong Hyuk
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.19 no.9
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    • pp.69-76
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    • 2018
  • The present study analyzed the effect of film hole position of 45 degree ribbed cooling channel on film cooling performance of gas turbine blades. We also investigated the influence of the ribs under the fixed blowing ratio. Three-dimensional numerical model was constructed and extensive simulation was conducted using the commercial code (Fluent ver. 17.0) under steady-state condition. Base on the simulation results, We investigated the cooling effectiveness, flow velocity, streamline, and pressure coefficient. Moreover, We analyzed the effect of cooling hole position on ejection of the secondary flow caused by the rib structure. From the results, It was found that internal flow of the cooling channel forms a vortex pair in the counterclockwise from the top side, and clockwise from the bottom side. For the channels with ribs, the vortex flow generated by the ribs caused a higher pressure difference near the hole outlet, resulting in at least 12% higher cooling effectiveness than the channel without ribs. Additionally, when the hole is located on the left side of the ribbed channel (Rib-Left), it can be found that the secondary flow generated by the ribs hits against wall surface near the hole to form a flow in the direction of the hole inclination angle. Therefore, It is considered that the region where the cooling gas discharged to the blade surface stays in the main flow boundary layer is wider than the other cases. In this case, The largest pressure coefficient difference was observed near the outlet of the hole, and as a result, the discharge of the cooling gas was accelerated and the cooling efficiency was slightly increased.

A Numerical Study on the Geometry Optimization of Internal Flow Passage in the Common-rail Diesel Injector for Improving Injection Performance (커먼레일 디젤인젝터의 분사성능 개선을 위한 내부유로형상 최적화에 관한 수치적 연구)

  • Moon, Seongjoon;Jeong, Soojin;Lee, Sangin;Kim, Taehun
    • Transactions of the Korean Society of Automotive Engineers
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    • v.22 no.2
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    • pp.91-99
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    • 2014
  • The common-rail injectors are the most critical component of the CRDI diesel engines that dominantly affect engine performances through high pressure injection with exact control. Thus, from now on the advanced combustion technologies for common-rail diesel injection engine require high performance fuel injectors. Accordingly, the previous studies on the numerical and experimental analysis of the diesel injector have focused on a optimum geometry to induce proper injection rate. In this study, computational predictions of performance of the diesel injector have been performed to evaluate internal flow characteristics for various needle lift and the spray pattern at the nozzle exit. To our knowledge, three-dimensional computational fluid dynamics (CFD) model of the internal flow passage of an entire injector duct including injection and return routes has never been studied. In this study, major design parameters concerning internal routes in the injector are optimized by using a CFD analysis and Response Surface Method (RSM). The computational prediction of the internal flow characteristics of the common-rail diesel injector was carried out by using STAR-CCM+7.06 code. In this work, computations were carried out under the assumption that the internal flow passage is a steady-state condition at the maximum needle lift. The design parameters are optimized by using the L16 orthogonal array and polynomial regression, local-approximation characteristics of RSM. Meanwhile, the optimum values are confirmed to be valid in 95% confidence and 5% significance level through analysis of variance (ANOVA). In addition, optimal design and prototype design were confirmed by calculating the injection quantities, resulting in the improvement of the injection performance by more than 54%.