• 한국항해항만학회지
• /
• 제47권3호
• /
• pp.174-181
• /
• 2023

일본 도쿄전력의 후쿠시마 원전 오염수 해양방류에 대해 한일해엽 연안 5개 지자체(제주, 전남, 경남, 부산, 울산)는 합동 대책위원회를 운영하고 있다. 본 연구는 제주연구원, 부산연구원, 울산연구원에서 일본 후쿠시마 원전 오염수 해양방류에 따른 대응 방안 연구의 일환으로 수행한 시민 설문조사, 대응 전략, 세부실천과제 등을 비교 분석하여 향후 타 연안도시 정책 입안자들이 실효성 있는 방안 마련을 위한 기초자료를 제시하는데 목적이 있다. 인식조사 결과 모든 지자체 시민들은 과학적 연구결과에 상관없이 해양방류에 대해 부정적 인식이 강한 것으로 나타나 향후 수산업, 관광업계의 피해가 클 것으로 예상된다. 지자체별 대응전략에서는 모든 지자체 공통으로 컨트롤 타워 구축이 가장 시급한 과제로 나타났다. 이는 실효성 있는 대응을 위해 공무원 조직 한계인 직제 중심에서 탈피하여 기능 중심 대응이 필요하기 때문이라고 판단된다. 또한 대응방법에 있어 제주와 부산은 분야별 대응방안을 수립한 반면, 울산시는 방류시점에 따른 단계별 대응방안으로 실질적 대응에 초점을 맞추고 있다. 내용적으로는 수산물 방사능 검사체계 구축, 국민의 불안감 해소를 위한 홍보가 중요한 것으로 나타났다. 향후 2030년까지 지속적으로 후쿠시마 원전 오염수의 해양방류가 예정되어 있는 만큼 지자체 연구기관 간 연구결과 및 성과 공유를 위한 네트워크강화가 필요할 것으로 판단된다.

• Food Science and Biotechnology
• /
• 제17권1호
• /
• pp.106-113
• /
• 2008

The antioxidant and anti-inflammatory protective effects of $\beta$-glucan from barley on RAW 264.7 murine macrophage cells induced by lipopolysaccharide (LPS) were examined. The RAW 264.7 murine macrophages were preincubated with various concentrations ($0-200\;{\mu}g/mL$) of $\beta$-glucan and stimulated with LPS to induce oxidative stress and inflammation. The $\beta$-glucan treatments were found to reduce thiobarbituric acid-reactive substance (TBARS) accumulation, and enhance glutathione levels and the activities of antioxidative enzymes, including superoxide dismutase (SOD), catalase, glutathione reductase, and glutathione peroxidase (GSH-px) in the LPS-stimulated macrophages as compared to the LPS-only treated cells. Nitric oxide (NO) production was significantly suppressed in a dose-dependent manner (p<0.05) with an $IC_{50}$ of $104\;{\mu}g/mL$. Further treatment with $\beta$-glucan at $200\;{\mu}g/mL$ suppressed NO production to 2% of the LPS-control, and suppressed the levels of inducible nitric oxide synthase (iNOS) protein and mRNA in a dose-dependent manner. The specific DNA binding activity of nuclear factor ${\kappa}B\;(NF{\kappa}B)$ was significantly suppressed by $\beta$-glucan treatment with an $IC_{50}$ of $220\;{\mu}g/mL$ in a dose-dependent manner. Finally, barley $\beta$-glucan ameliorates NO production and iNOS expression through the down-regulation of $NF{\kappa}B$ activity, which may be mediated by attenuated oxidative stress in RAW 264.7 macrophages.

• 한국산업보건학회지
• /
• 제25권1호
• /
• pp.27-35
• /
• 2015

Objectives: To investigate safety and health management, conditions in factories or facilities handling radiation-generating devices and radioactive isotopes were reviewed in terms of regulations of radiation safety control in Korea. Radiation exposure levels generated at those facilities were directly measured and evaluated for establishing an effective safety and health management plan. Methods: Government organizations with laws and systems of radiation safety and health were investigated and compared. There are three laws governing radiation-related employment such as occupational safety and health acts, nuclear safety acts, and medical service acts. We inspected 12 workplaces as research objects:four workplaces that manufacture and assemble semiconductor devices, three non-destructive inspection workplaces that perform inspections on radiation penetration, and five workplaces in textile and tire manufacturing. Monitoring of radiation exposure was performed through two methods. Spatial and surface monitoring using real-time radiation instruments was performed on each site handling radiation generating devices and radioactive isotopes in order to identify radiation leakage. Results: According to the occupational safety and health act, there is no legal obligation to measure ionizing radiation and set dose limits. This can cause confusion in the application of the laws, because the scopes and contents are different from each other. Surface dose rates in radiation generating devices such as implanters, thickness gages and accelerators, which were registered according to nuclear safety acts, using surveymeters, and seven of 36 facilities(19.4%) exceeded the international standards for surface radiation dose of $10{\mu}Sv/hr$. Conclusions: The results showed that occupational health and safety acts require a separate provision for measuring and assessing the radiation exposure of workers performing radiation work. Like noise, ionizing radiation will also periodically be controlled by including it in the object factors of work-environment measurement.

• 대한기계학회:학술대회논문집
• /
• 대한기계학회 2004년도 추계학술대회
• /
• pp.166-171
• /
• 2004

Since early 1950's fracture mechanics has brought significant impact on structural integrity assessment in a wide range of industries such as power, transportation, civil and petrochemical industries, especially in nuclear power plant industries. For the last two decades, significant efforts have been devoted in developing defect assessment procedures, from which various fitness-for-purpose or fitness-for-service codes have been developed. From another aspect, recent advances in IT (Information Technologies) bring rapid changes in various engineering fields. IT enables people to share information through network and thus provides concurrent working environment without limitations of working places. For this reason, a network system based on internet or intranet bas been appeared in various fields of business. Evaluating the integrity of structures is one of the most critical issues in nuclear industry. In order to evaluate the integrity of structures, a complicated and collaborative procedure is required including regular in-service inspection, fracture mechanics analysis, etc. And thus, experts in different fields have to cooperate to resolve the integrity problem. In this paper, an internet-based cooperative system for integrity evaluation system which adapts IT into a structural integrity evaluation procedure for reactor pressure vessel is introduced. The proposed system uses Virtual Reality (VR) technique, Virtual Network Computing (VNC) and agent programs. This system is able to support 3-dimensional virtual reality environment and to provide experts to cooperate by accessing related data through internet.

• Nuclear Engineering and Technology
• /
• 제38권3호
• /
• pp.293-300
• /
• 2006

A liquid metal reactor (LMR) operated at high temperatures is subjected to both cyclic mechanical loading and thermal loading; thus, creep-fatigue is a major concern to be addressed with regard to maintaining structural integrity. The Korea Advanced Liquid Metal Reactor (KALIMER), which has a normal operating temperature of $545^{\circ}C$ and a total service life time of 60 years, is composed of various cylindrical structures, such as the reactor vessel and the reactor baffle. This study focuses on the creepfatigue crack initiation for a cylindrical Y-junction structure made of 316 stainless steel (SS), which is subjected to cyclic axial tensile loading and thermal loading at a high-temperature hold time of $545^{\circ}C$. The evaluation of the considered creep-fatigue crack initiation was carried out utilizing the ${\sigma}_d$ approach of the RCC-MR A16 guide, which is the high-temperature defect assessment procedure. This procedure is based on the total accumulated strain during the service time. To confirm the evaluated result, a high-temperature creep-fatigue structural test was performed. The test model had a circumferential through wall defect at the center of the model. The defect front of the test model was investigated after the $100^{th}$ cycle of the testing by utilizing a metallurgical inspection technique with an optical microscope, after which the test result was compared with the evaluation result. This study shows how creep-fatigue crack initiation for a high-temperature structure can be predicted with conservatism per the RCC-MR A16 guide.

• Journal of Radiation Protection and Research
• /
• 제36권1호
• /
• pp.35-43
• /
• 2011

The PHENIX Experiment is the largest of the four experiments that have taken data at the Relativistic Heavy Ion Collider. PHENIX, the Pioneering High Energy Nuclear Interaction eXperiment, is designed specifically to measure direct probes of the collisions such as electrons, muons, and photons. The primary goal of PHENIX is to discover and study a new state of matter called the Quark-Gluon Plasma. Among many particles, muons coming from W-boson decay gives us key information to analyze the spin of proton. Resistive plate chambers are proposed as a suitable solution as a muon trigger because of their fast response and good time resolution, flexibility in signal readout, robustness and the relatively low cost of production. The RPC detectors for upgrade were assembled and their performances were evaluated. The procedure to make the detectors better was optimized and described in detail in this thesis. The code based on ROOT was written and by using this the performance of the detectors made was evaluated, and all of the modules for north muon arm met the criteria and installation at PHENIX completed in November 2009. As RPC detectors that we made showed fast response, capacity of covering wide area with a resonable price and good spatial resolution, this will give the opportunity for applications, such as diagnosis and customs inspection system.

• 한국화재소방학회논문지
• /
• 제27권5호
• /
• pp.26-31
• /
• 2013

원전의 가압기 지지대에 사용되는 볼트는 설계 시 안전율 측면에서 충분한 경도의 볼트를 사용하지만, 현장실사를 통해 허용 경도 범위를 초과하는 볼트가 일부 확인되었다. 이러한 높은 경도의 볼트는 응력부식 및 재료의 파괴인성이 취약하고, 가압기는 부식에 취약한 환경이므로 이 부분에 대한 검토가 필요하다. 따라서 본 연구에서는 현장실사를 통해 원전 가압기 지지대에 사용되는 볼트의 경도를 측정하였고, 이를 통해 응력부식과 부재의 파괴인성에 의한 균열을 제한할 수 있는 최대 허용응력을 계산하였다. 또한 정상운전 및 사고운전 시 발생할 수 있는 지지대 볼트의 응력을 수치해석 프로그램인 ANSYS를 사용하여 예측하였고, 이 응력이 응력부식을 제한할 수 있는 최대 허용응력 내에 있는 지 검토하였다. 검토 결과 정상 및 사고운전 조건에서 볼트의 응력은 응력부식에 대해 허용응력 안전 기준치를 만족하는 것으로 나타났다. 그러나 향후 가압기 지지대의 구조물 체결방법을 체결 절차에 반영하여 정비 시 가압기의 건전성을 확보할 수 있도록 검토가 필요하다.

• 대한핵의학회지
• /
• 제21권2호
• /
• pp.155-165
• /
• 1987

The noninvasive nature of the radionuclide angiocardiography provided a useful approach for the evaluation of left-to-right cardiac shunts (LRCS). While the qualitative information can be obtained by inspection of serial radionuclide angiocardiograms, the quantitative information of radionuclide angiocardiography can be obtained by the analysis-of time-activity curves using advanced computer system. The count ratios method and pulmonary-to-systemic flow ratio (QP/QS) by gamma variate fit method were used to evaluate the accuracy of detection and localization of LRCS. One hundred and ten time-activity curves were analyzed. There were 46 LRCS (atrial septal defects 11, ventricular septal defects 22, patent ductus arteriosus 13) and 64 normal subjects. By computer analysis of time-activity curves of the right atrium, ventricle and the lungs separately, the count ratios modified by adding the mean cardiac transit time were calculated in each anatomic site. In normal subjects the mean count ratios in the right atrium, ventricle and lungs were 0.24 on average. In atrial septal defects, the count ratios were high in the right atrium, ventricle and lungs, whereas in ventricular septal defects the count ratios were higher only in the right ventricle and lungs. Patent ductus arteriosus showed normal count ratios in the heart but high count ratios were obtained in the lungs. Thus, this count ratios method could be separated normal from those with intra cardiac or extracardiac shunts, and moreover, with this method the localization of the shunt level was possible in LRCS. Another method that could differentiate the intracardiac shunts from extracardiac shunts was measuring QP/QS in the left and right lungs. In patent ductus arteriosus, the left lung QP/QS was higher than those of the right lung, whereas in atrial septal defects and ventricular septal defects QP/QS ratios were equal in both lungs. From this study, it was found that by measuring QP/QS separately in the lungs, intracardiac shunt could be differenciated from extracardiac shunts.

• 비파괴검사학회지
• /
• 제24권4호
• /
• pp.378-383
• /
• 2004

국내 원자력발전소의 Class1과 Class2 배관검사에 적용할 수 있는 초음파탐상 검사자, 장비 그리고 절차서에 대한 한국형 기량검증(KPD) 시스템을 구축하였다. PD 방법을 적용한 검사결과와 전통적인 dB-drop 방법을 이용한 검사결과를 상호 비교하기 위하여 Round Robin Test(RRT)를 수행하였다. RRT 결과는 PD 방법의 신뢰성이 dB Drop 방법보다 우수한 것으로 나타났다. 이러한 결과로부터 원자력발전소 가동중검사에 PD 방법을 적용함으로써 초음파탐상검사 결과의 신뢰성이 더욱 향상될 것으로 기대된다.

• 방사선산업학회지
• /
• 제18권1호
• /
• pp.95-100
• /
• 2024

To establish a radioactive waste life cycle history management system, a series of processes including waste generation, classification, packaging, storage, transportation, and disposal were reflected in the information management system. A preliminary review process was introduced to reduce the amount of radioactive waste generated and manage it efficiently. Through this, the amount of radioactive waste generated must be checked from the beginning of the research, and the generated radioactive waste must be thoroughly managed from the stage of generation to final disposal. In particular, in the case of radioactive waste data generated during nuclear facility operation and each experiment, a radioactive waste information management system must be operated to receive information from the waste generator and integrate it with processing information at the management stage. The application process for small-package containers was reflected so that information such as the generation facility of radioactive waste, generation facility, project information, types of radioactive waste, major radionuclides, etc. In the radioactive waste management process, the preceding steps are to receive waste history from the waste generators. This includes an application for a specified container with a QR label, pre-inspection, and management request. Next, the succeeding steps consist of repackaging, treatment, characterization, and evaluating the suitability of disposal, for a process to transparently manage radioactive wastes.