정부(해양수산부) 및 관계기관에서는 안전관리 취약선박의 해양안전 증진을 위한 많은 정책을 시행하고 있으나, 선박의 안전관리에 대한 위험성평가 부재로 각 제도의 효과성에 다소 아쉬움이 확인되었다. 선박의 위험성평가에 대한 국내 선행연구는 대부분 개별적 해양사고 위험성에 대한 단편적 위험성만을 취급하고 있어 포괄적 해양사고 위험성평가를 위한 새로운 방식이 필요하다. 선박의 안전관 리에 대한 포괄적 위험성평가 적용사례로 항만국통제와 노르웨이 해사국의 점검대상 선정방법이 있다. 본 연구에서는 국내 해양사고 및 등록현황의 높은 비중을 차지하고 있는 연근해어선을 대상으로 포괄적 선박안전관리 위험성평가를 위한 지표를 개발하고 적용하였다. 그 결과, 각 선박별 위험성을 계량적 수치로 확인하였고, 개별적 안전관리 취약요소의 순위를 식별하였다.

In this study, algorithms for analyzing the torsion of buildings under earthquake excitation are developed. The algorithm and formulations to account for the torsional angle are verified by analyzing the seismic acceleration time history data. The method was applied to the reference buildings to examine their operation and usability. The reference application demonstrated that the noise-canceling scheme successfully overcame various obstacles in the field measurements. The developed method is expected to be used as a tool to support a loss assessment system for determining the direction and priority of disaster response in the event of an earthquake.

유방조직 확장기(BTE)는 MR 금기로 분류되고 있으나 이전 연구들에서 제한적인 조건에서 MRI 검사가 가능함을 발표하였다. 본 연구는 미국재료시험 협회에서 권고하는 변위력과 토크뿐 만 아니라 뒤틀림을 측정하여 MR 안전성을 평가하였다. 3.0 T MRI 장치와 350 ㎖, 650 ㎖ BTE를 사용하였다. 변위력은 자기장이 가장 큰 지점에서 측정 기구에 BTE를 매달고 발생된 최대 변위각을 3회씩 측정하였다. 토크는 원형 용기에 생리식염수를 단계적으로 채운 BTE를 놓고 자기장에 의해 발생된 회전력을 45˚ 간격에서 정성적으로 측정하였다. 뒤틀림은 생리식염수를 최대로 채운 뒤 자성 밸브의 뒤틀림 각도를 포켓 경사계를 이용하여 두부, 어깨, 유방, 간, 골반이 중심일 때 유방 위치에서 각각 측정하였다. 측정 결과 변위각 은 350 ㎖의 경우 0 ㏄, 150 ㏄에서 각각 125˚, 54.3˚, 650 ㎖은 0 ㏄에서만 123.3˚로 MR 금기 기준을 초과했다. 토크는 350 ㎖의 경우 모두 +4로 측정되었고, 650 ㎖의 경우 450 ㏄ 생리식염수 미만에서는 모두 +4, 550 ㏄ 이상에서는 +1∼+4로 나타났으며, 일부를 조건을 제외하고 모두 MR 금기 조건을 초과했다. 뒤틀림은 350 ㎖의 경우 5˚∼80˚ 를 나타냈으며. 650 ㎖는 15˚∼90˚를 나타내어 환자에게 통증 유발 가능성을 확인했다. BTE의 변위각, 토크, 뒤틀림을 측정하여 MR 금기로 평가하였으며, 어떠한 조건하에서도 MR 환경에서 환자의 안전을 보장할 수 없다.

Radiological impact analyses were carried out for a near-surface radioactive waste repository at Gyeongju in South Korea. The RESRAD-ONSITE code was applied for the estimation of maximum exposure doses by considering various exposure pathways based on a land area of 2,500 m2 with a 0.15 m thick contamination zone. Typical influencing input parameters such as shield depth, shield materials’ density, and shield erosion rate were examined for a sensitivity analysis. Then both residential farmer and industrial worker scenarios were used for the estimation of maximum exposure doses depending on exposure duration. The radiation dose evaluation results showed that 60Co, 137Cs, and 63Ni were major contributors to the total exposure dose compared with other radionuclides. Furthermore, the total exposure dose from ingestion (plant, meat, and milk) of the contaminated plants was more significant than those assessed for inhalation, with maximum values of 5.5×10−4 mSv‧yr−1 for the plant ingestion. Thus the results of this study can be applied for determining near-surface radioactive waste repository conditions and providing quantitative analysis methods using RESRAD-ONSITE code for the safety assessment of disposing radioactive materials including decommissioning wastes to protect human health and the environment.

In general, companies operate systematically in response to financial risks such as exchange rates and liquidity, while they are vulnerable to risks in the manufacturing and sales processes. In particular, logistics refers to the activities for planning, managing and implementing efficient flows from the starting point of goods and products to the point of consumption, The purpose of this study was to develop key risks and key risk management indicators (KRIs) for risks that undermine logistics efficiency so that logistics risks can be effectively prevented and managed. As a result, 40 risk management indicators (KRIs) were developed in a total of six categories in the logistics sector, and the definition, calculation method and early warning grade of each KRI were presented so that companies could prevent risks in advance in logistics activities and contribute to enhancing efficiency of their work.

The Korea Atomic Energy Research Institute (KAERI) has developed geological repository systems for the disposal of high-level wastes and spent nuclear fuels (SNFs) in South Korea. The purpose of the most recently developed system, the improved KAERI Reference Disposal System Plus (KRS+), is to dispose of all SNFs in Korea with improved disposal area efficiency. In this paper, a system-level safety assessment model for the KRS+ is presented with long-term assessment results. A system-level model is used to evaluate the overall performance of the disposal system rather than simulating a single component. Because a repository site in Korea has yet to be selected, a conceptual model is used to describe the proposed disposal system. Some uncertain parameters are incorporated into the model for the future site selection process. These parameters include options for a fractured pathway in a geosphere, parameters for radionuclide migration, and repository design dimensions. Two types of SNF, PULS7 from a pressurized water reactor and Canada Deuterium Uranium from a heavy water reactor, were selected as a reference inventory considering the future cumulative stock of SNFs in Korea. The highest peak radiological dose to a representative public was estimated to be 8.19×10-4 mSv‧yr-1, primarily from 129I. The proposed KRS+ design is expected to have a high safety margin that is on the order of two times lower than the dose limit criterion of 0.1 mSv‧yr-1.

The operational safety assessment is an important part of a safety case for the deep geological repository of spent fuels. It consists of different stages such as the identification of initiating events, event tree analysis, fault tree analysis, and evaluation of exposure doses to the public and radiation workers. This study develops a probabilistic safety assessment method for the operational safety assessment and establishes an assessment framework. For the event and fault tree analyses, we propose the advanced information management system for probabilistic safety assessment (AIMS-PSA Manager). In addition, we propose the Radiological Safety Analysis Computer (RSAC) program to evaluate exposure doses to the public and radiation workers. Furthermore, we check the applicability of the assessment framework with respect to drop accidents of a spent fuel assembly arising out of crane failure, at the surface facility of the KRS+ (KAERI Reference disposal System for SNFs). The methods and tools established through this study can be used for the development of a safety case for the KRS+ system as well as for the design modification and the operational safety assessment of the KRS+ system.