• 대한수의학회지
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• 제55권4호
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• pp.227-232
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• 2015

Akabane and bovine ephemeral fever (BEF) viruses cause vector-borne diseases. In this study, inactivated Akabane virus (AKAV)+Bovine ephemeral fever virus (BEFV) vaccines with or without recombinant vibrio flagellin (revibFlaB) protein were expressed in a baculovirus expression system to measure their safety and immunogenicity. Blood was collected from mice, guinea pigs, sows, and cattle that had been inoculated with the vaccine twice. Inactivated AKAV+BEFV vaccine induced high virus neutralizing antibody (VNA) titer against AKAV and BEFV in mice and guinea pigs. VNA titers against AKAV were higher in mice and guinea pigs immunized with the inactivated AKAV+BEFV vaccine than in animals inoculated with vaccine containing revibFlaB protein. Inactivated AKAV+BEFV vaccine elicited slightly higher VNA titers against AKAV and BEFV than the live AKAV and live BEFV vaccines in mice and guinea pigs. In addition, the inactivated AKAV+BEFV vaccine was safe, and induced high VNA titers, ranging from 1 : 64 to 1 : 512, against both AKAV and BEFV in sows and cattle. Moreover, there were no side effects observed in any treated animals. These results indicate that the inactivated AKAV+BEFV vaccine could be used in cattle with high immunogenicity and good safety.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.417-422
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• 1998

he Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3&4(UCN 3&4) has been improved from the Yonggwang Nuclear Power Plant Units 3&4(YGN 3&4) based on the evaluation results for depressurization capability tests performed at YGN 3&4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown Phenomena in order to optimize the orifice size of UCN 3&4 RCGVS. Baesd on these analyses results, the RCGVS orifice size for UCN 3&4 has been reduced to 9/32 inch from the l1/32 inch for YGN 3&4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3&4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation.

• Nuclear Engineering and Technology
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• 제40권4호
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• pp.269-276
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• 2008

Operational license of WWER-440/213 units at Paks NPP, Hungary is limited to the design lifetime of 30 years. Prolongation by additional 20 years of the operational lifetime is feasible. Moreover, enhancement of the reactor thermal power by 8% will increase both the net power output and the competitiveness of the plant. Paks NPP is a pioneer considering the power up-rate and preparation of long-term operation of WWER-440/213 design. Systematic preparatory work for long-term operation of Paks NPP has been started in 2000. A regulatory framework and a comprehensive engineering practice have been developed. According to the authors view, creation of a gapless engineering system via consequent application of best practices, and feed-back of experiences together with proper consideration of WWER-440/V213 features are the decisive elements of ensuring the safety of long-term operation. That systematic engineering approach is in the focus of recent paper. Key elements of justification and measures for ensuring the safety of long-term operation of Paks NPP WWER-440/213 units are identified and discussed. These are the assessment of plant condition and review of adequacy of ageing management programmes, also the review, validation and reconstitution of time limited ageing analyses as core tasks of licence renewal.

• Nuclear Engineering and Technology
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• 제51권2호
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• pp.561-572
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• 2019

In the design criterion for the nuclear power plant piping system, the limit state of the piping against an earthquake is assumed to be plastic collapse. The failure of a common piping system, however, means the leakage caused by the cracks. Therefore, for the seismic fragility analysis of a nuclear power plant, a method capable of quantitatively expressing the failure of an actual piping system is required. In this study, it was conducted to propose a quantitative failure criterion for piping system, which is required for the seismic fragility analysis of nuclear power plants against critical accidents. The in-plane cyclic loading test was conducted to propose a quantitative failure criterion for steel pipe elbows in the nuclear power plant piping system. Nonlinear analysis was conducted using a finite element model, and the results were compared with the test results to verify the effectiveness of the finite element model. The collapse load point derived from the experiment and analysis results and the damage index based on the stress-strain relationship were defined as failure criteria, and seismic fragility analysis was conducted for the piping system of the BNL (Brookhaven National Laboratory) - NRC (Nuclear Regulatory Commission) benchmark model.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1871-1880
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• 2020

Round robin analyses for vessel failure probabilities due to PTS events are proposed for plant-specific analyses of all types of reactors developed in Korea. Four organizations, that are responsible for regulation, operation, research and design of the nuclear power plant in Korea, participated in the round robin analysis. The vessel failure probabilities from the probabilistic fracture mechanics analyses are calculated to assure the structural integrity of the reactor pressure vessel during transients that are expected to initiate PTS events. The failure probabilities due to various parameters are compared with each other. All results are obtained based on several assumptions about material properties, flaw distribution data, and transient data such as pressure, temperature, and heat transfer coefficient. The realistic input data can be used to obtain more realistic failure probabilities. The various results presented in this study will be helpful not only for benchmark calculations, result comparisons, and verification of PFM codes developed but also as a contribution to knowledge management for the future generation.

• 한국안전학회지
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• 제18권3호
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• pp.88-93
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• 2003

The Process Safety Management (PSM) by the Law of Industry, Safety and Health has been performed for preventing major accidents of chemical plants since 1996. In terms of preventing chemical accidents more precisely, it is essential to develop a tool for quantitative risk assessment. For this, KOSHA (Korea Occupational Safety and Health Agency) developed an Integrated Risk Management System (IRMS). The system is designed to assimilate data on chemical plant hazards from external database, to integrate these data with location information(topographic and demographic), and to make them user-friendly accessible. The system consists of several main functions: display of five major Korean petrochemical complex layout display of equipment layout with its information utilizing the external database, zonation of the hazard effected area with consequence analyses, the most probable accident scenario generation, accident/incident database and calculation of frequency of accident using equipment reliability database, etc. The highlight of IRMS is to provide the risk contours using GIS(Geographical Information System) technology. IRMS is intended to manage hazardous installation more systematically and effectively, to reduce the number of accident remarkably, further minimizing production loss in the plant. The system is now under application to about 500 PSM sites as well as and emergency authorities in Korea by KOSHA (Korea Occupational Safety and Health Agency)

• 한국심리학회지 : 문화 및 사회문제
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• 제13권3호
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• pp.1-21
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• 2007

본 연구에서는 1) 원자력 발전소 지역 주민들의 안전체감을 구성하고 있는 하위요인들을 규명하고, 2) 그 구성요소들의 측정을 통해 주민들의 안전체감지수를 산출하며, 3) 주민들이 체감하는 안전의 정도와 발전소 직원들이 추측하는 주민들의 안전 체감 정도를 비교하였다. 이를 위해 원자력 발전소 지역주민 800명을 대상으로 연구 1과 발전소 직원 187명을 대상으로 연구 2가 수행되었다. 연구 결과에 따르면, 안전체감은 커뮤니케이션, 신뢰, 발전소 위험대응역량, 그리고 응급대응역량의 4가지 요소로 구성되어 있는 것으로 밝혀졌다. 개발된 안전체감 지수에 따르면 발전소 지역 주민들의 안전체감 수준은 매우 낮았으며(100점 만점에 38.22점), 이 점수는 발전소 지역에 따라 다른 것으로 나타났다. 또한 원자력 발전소의 직원들은 주민들이 실제로 체감하고 있는 것보다 주민들이 발전소를 훨씬 더 안전하게 지각하고 있을 것이라고 착각하고 있는 것으로 나타났다. 이 결과의 시사점 및 후속 연구에 대해 논의하였다.

• 한국안전학회지
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• 제11권4호
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• pp.135-142
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• 1996

Prolonged in-plant personnel exposure to high noise levels results in permant hearing damage. There are no way to correct this hearing damage by treatment or use of hearing aids. Therefore, every employer is responsible for providing a workplace free of such hazards as excessive noise. This study was carried out to evalute and predict a given noise environment based on specific limit as the noise guarantee for a newly-founded petrochemical plant. The maximum total sound level should not exceed 85dBA in the work area, except where the area is defined as a restricted area and 70dBA at the plant boundary. Prediction of the noise levels within the plant area for a newly-founded petrochemical plant was achieved by dividing all plant area into 20m$\times$20m regular grid spaces and noise level inside the area or unit that in-plant personel exposure to high noise levels was estimated computed into 5m$\times$5m regular grid spaces. The noise level at the grid point that was propagated from each of the noise sources(equipments) computed using the methematical formula was defined as follows : $SPL_2$=$SPL_1-20log{\frac{r_2}{r_1}}$(dB) where $SPL_1$ =sound pressure level at distance $r_1$ from the source $SPL_2$=sound pressure level at distance $r_2$ from the source As a result, the equipments exceeded noise limit or irritaring noise levels were identified on the specific grid coordinates. As for equipments in the area that show high noise levels, appropriate counter-measures for noise control (by barriers, enclosure, silencers, or the change of equipments, for example) should be reviewed. Methods for identifying sources of noise applied in this study should be the model for prediction of the noise levels for any newly-founded plant.

• 농약과학회지
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• 제14권4호
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• pp.339-346
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• 2010

본 연구는 생리활성이 높은 식물오일의(라벤더, 레몬유칼립투스 및 계피 오일) 친환경 살충소재의 활용가능성을 탐색하고자 급성독성(급성경구독성, 급성경피독성, 피부자극성 및 안점막자극성)시험을 수행하였다. 랫드를 이용한 급성경구독성시험결과 라벤더, 레몬 유칼립투스 및 계피 오일의 $LD_{50}$은 2,000 mg/kg bw 이상이었고, 급성경피독성시험결과 모든 시험물질의 $LD_{50}$이 4,000 mg/kg bw으로 나타났다. 피부자극성시험결과 라벤더와 레몬 유칼립투스 오일은 자극성이 없었고, 계피 오일은 중도의 자극성을 나타냈다. 안점막자극성시험결과 라벤더, 레몬 유칼립투스 오일은 자극성이 없었고, 계피오일은 중도의 자극성을 나타냈으나 세척시험 결과 자극성은 없었다. 따라서, 라벤더 및 레몬 유칼립투스 오일은 독성이 낮았으나, 계피 오일은 중도의 피부자극성 및 안점막자극성을 갖는 것으로 평가되었다.

• Korean Chemical Engineering Research
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• 제52권4호
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• pp.475-480
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• 2014

플랜트 배치 최적화 문제의 목적은 장치를 연결하는 파이프의 길이를 최소화 하는데 있다. 하지만, 기존 연구들은 대체적으로 단일 층의 배치 문제를 다루고 있으며, 또한 장치 간 유지 보수에 필요한 최소 공간 확보, 사고 예방을 위한 장치 간 이격 거리등 안전 요소를 간과해 왔다. 본 연구에서는 장치 간 유지 보수에 필요한 최소 거리 확보 및 안전 이격 거리를 고려하여 플랜트 배치 문제를 MILP(Mixed Integer Linear Programming) 형태의 문제로 정의하였다. 본 문제의 목적함수는 장치 간 연결하는 파이프 비용이며 제약조건은 안전을 위한 장치 간 최소 이격 거리, 유지 보수에 필요한 공간으로 설정하였다. 하지만, 공정 특성에 따라 필요한 공간 및 작업자의 통행 등 다양한 제약조건을 수반하게 된다. 이에 따라 플랜트 배치 문제를 일반적인 수학식으로 표현하는 데 많은 제약이 있으며, 따라서 함수의 미분식을 이용하는 기존 최적화 방법론을 이용하여 문제를 해결하는 데 많은 어려움이 있다. 본 연구에서는 함수의 미분식을 적용하지 않고 이용이 가능한 경험적 최적화 기법 중 하나인 PSO(Particle Swarm Optimization)를 이용하여 최적화를 수행하였다. 본 연구에서 개발한 모델의 검증을 위해 Ethylene Oxide 공정을 2층으로 배치하는 최적화를 수행하였다.