• 한국산업보건학회지
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• 제15권3호
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• pp.192-201
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• 2005

The Korean government had introduced the industrial safety & hygiene consultant(ISHC) system to improve worksite health and safety level by providing specialized industrial safety & hygiene(S&H) services in 1996. Despite of initial hopeful expectation it has been said that this plan might fail to settled down and maintain its purpose. This study was designed to investigate operational issues and problems concerning the ISHC system, that would direct the way of change and future role. Questionnaire were sent to ISHC, professional engineer, agencies for occupational injury prevention, S&H specialist in the corporation nationwide and totally 256 people responded to in having 62.7% of response rate. The result of this study were as follows; 1. One hundred and forty two cases of safety assessment and 27 cases of process safety reports were the six years' results since 1996 the ISHC program had first been introduced. This results showed that injury prevention activities of ISHC had been stagnant. 2. The 78.8% of respondents had negative opinion about injury prevention activities of ISHC program. 3. The operational problems of ISHC were lack of understanding of company about ISHC, low systematization of work items, duty overlapping with agencies for occupational injury prevention, low support by government. in order. 4. It was suggested that abolition of ISHC and promotion of professional engineer system should be considered. 5. To promote professional engineer system it was suggested that the professional engineer could conduct consulting service and ISHC should be integrated with the expert system.

• 방사성폐기물학회지
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• 제6권4호
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• pp.329-346
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• 2008

중저준위 방사성폐기물의 영구처분을 위하여 건설되는 월성원자력환경관리센터의 1단계 폐쇄후 안전성평가에 대하여 기술하였다. 처분시설의 건설운영허가를 위하여 작성된 안전성평가에 대하여 평가개요, 처분시설의 폐쇄개념, 처분부지에 대한 지하수 유동특성을 이용하여 평가를 위한 시나리오의 개발과정과 도출된 평가대상 시나리오에 대한 개념을 기술하였다. 폐쇄후 안전성평가 모델링을 위한 평가도구, 입력인자와 개별 시나리오에 대한 핵종누출 모델링, 기체발생 및 기체이동 모델링, 인간침입 모델링과 생태계 모델링에 대하여 기술하였다. 처분시설의 폐쇄후 안전성 평가시나리오에 대하여 국내 규제치를 만족하는 것으로 평가되었으며 향후 처분시설 안전성에 대한 불확실성 저감과 신뢰성 증진을 위한 노력을 지속적으로 수행할 예정이다.

• 한국안전학회지
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• 제29권4호
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• pp.160-167
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• 2014

To determine a proper ASIL for each hazardous event with a proper safety goal, the right classes should first be determined for the three properties of the hazardous event; (i) severity of harm from the resultant accident, (ii) exposure to the relevant operational situation, and (iii) controllability to avoid the induced risks. ASIL can be clearly determined with right classes of these three properties. But no specific methodologies or processes for their classification can be found in ISO 26262, except only a rough guideline with a simplified set of illustrative tables. In this paper, we try to present a systematic model for classifying the three properties of the hazardous event and suggest a refined procedure of ASIL determination. The proposed model provides a specific method to get a more objective ASIL compared with that in the standard. Scrutinizing the current methodology, we develop a refined method and also provide an illustrative example.

• 한국항공운항학회지
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• 제23권2호
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• pp.1-6
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• 2015

The RSA is intended to prevent the following five types of events from becoming an accident: landing overruns, landing undershoots, landing veer-offs, takeoff overruns and takeoff veer-offs. The improved models are based on evidence from worldwide accidents and incidents that occurred during the past 27 years. The analysis utilizes historical data from the specific airport and allows the user to take into consideration specific operational conditions to which movements are subject, as well as the actual or planned RSA conditions in terms of dimensions, configuration, type of terrain, and boundaries defined by existing obstacles. This paper shows how to apply the improved models for Risk Assessment of Runway Safety Areas (Airport cooperative research program(ACRP) Report 50) into an airport and the outcome differences between the old models based on ACRP report 3-Analysis of aircraft overrun and undershoots for runway safety areas and the new models from ACRP report 50 in the specific airport.

• 한국항해항만학회:학술대회논문집
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• 한국항해항만학회 2006년도 International Symposium on GPS/GNSS Vol.1
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• pp.435-440
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• 2006

The Reduced Vertical Separation Minimum (RVSM), which is the reduced minimum from 2,000 ft to 1,000 ft at flight levels (FL) between 290 and FL410 inclusive, was implemented in 30 September 2005 within the Japanese domestic airspace. Prior to the implementation, safety assessment for the airspace in assumed RVSM environments was carried out. Some model parameter values of collision risk model were estimated using flight plan (progress) data and radar data. An estimate of vertical collision risk including operational risk was calculated using these together with given parameter values. The results obtained from this analysis are as follows. (1) Contribution of the vertical collision risk for the crossing routes is about 9 percents of the total technical risk. (2) The estimate of the collision risk is $4.1{\times}10^{-9}$ [fatal accidents / flight hour] and the value is smaller than a maximum allowable level of collision risk, i.e. $5{\times}10^{-9}$ [fatal accidents / flight hour], called the Target Level of Safety.

• 해양환경안전학회:학술대회논문집
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• 해양환경안전학회 2017년도 공동학술발표회
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• pp.232-232
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• 2017

• 해양환경안전학회지
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• 제13권2호
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• pp.133-140
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• 2007

예로부터 선장은 경험적으로 기상, 선박 제원 상태 및 운항 일정을 고려하여 최적의 항로를 선택하여 항해하여 왔다. 이는 선장의 경험을 바탕으로 해류나 파랑에 대한 기상 예보 정보를 활용하여 최적항로를 결정하는 것으로 아직까지 선상에서 항로 결정을 보조해주는 디지털화한 시스템은 그 사례를 찾아보기 힘들다. 본 논문에서는 선박의 운항 효율성과 안전성의 관점에서 구성된 선상 최적 항로 안전 평가 시스템을 소개한다. 선사와 선장이 요구하는 효율적인 항해를 위해서는 도착예정시간 및 연료소모량을 최소로 하는 최적 항로를 구한다. 이는 선박의 파랑 중 부가저항에 기초를 둔 선속 저하 빚 마력 증가를 고려하여 계산한다. 안전성 관점에서는 3D 판넬법에 기초를 둔 선박의 내항 계산을 본 시스템에서 구현하여 내항 평가를 수행하며, 최종적으로 선박의 항로 안전 계획 및 평가를 위한 보조 수단이다.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1784-1791
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• 2020

The 14 MeV neutron generator facility is being developed by the Institute for Plasma Research India to conduct the lab scale experiments related to Indian breeding blanket system for ITER and DEMO. It will also be utilized for material testing, shielding experiments and development of fusion diagnostics. Occupational radiation exposure control is necessary for the all kind of nuclear facilities to get the operational licensing from governing authorities and nuclear regulatory bodies. In the same way, the radiation exposure for the 14 MeV neutron generator facility at the occupational worker area and accessible zones for general workers should be under the permissible limit of AERB India. The generator is designed for the yield of 10¹² n/s. The shielding assessment has been made to estimate the radiation dose during the operational time of the neutron generator. The facility has many utilities and constraints like ventilation ducts, accessible doors, accessibility of neutron generator components and to conduct the experiments which make the shielding assessment challenging to provide proper safety for occupational workers and the general public. The neutron and gamma dose rates have been estimated using the MCNP radiation transport code and ENDF -VII nuclear data libraries. The ICRP-74 fluence to dose conversion coefficients has been used for the assessment. The annual radiation exposure has been assessed by considering 500 h per year operational time. The provision of local shield near to neutron generator has been also evaluated to reduce the annual radiation doses. The comprehensive results of radiation shielding capability of neutron generator building and local shield design have been presented in the paper along with detailed maps of radiation field.

• 한국전산구조공학회논문집
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• 제18권1호
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• pp.93-99
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• 2005

최근, 제철소, 원자력 및 수${\cdot}$화력 발전소 등 주요 기간설비에 있어서 해당 구조물, 관련 장비들의 노후화에 따른 고장진단, 수리보수, 안전성 평가와 잔여 수명 예측을 통한 수명연장에 관련된 요구가 높아지고 있다. 손상발생 시나리오의 구축, 정밀해석기법의 확립, 위험성 혹은 신뢰성 평가기술 개발 등에 관한 연구가 이러한 요구를 반영하여 활발하게 수행되고 있다. 본 연구에서는 구조물의 안전성 평가분야에서 가장 활발하게 사용되는 유한요소해석기술을 이용하여 제철설비 구조물의 안전성을 평가하는 절차를 개발하고 실제 가동 중인 고로를 대상으로 적용하여 유용성을 검토하였다.

• 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.