Currently, Korea is planning to use various equipments and technologies for cutting, decontamination, compression, solidification, and packaging at decommissioning site of Kori unit 1 and Wolsung unit 1. In particular, Korea is considering to apply new technologies like inorganic acid decontamination, spent resion treatment technology not only to localize various decommissioning technology, but to meet the limit of 14,500 drums of the decommissioning waste per unit. However, before the techniques applied to decommissioning, it is necessary to demonstrate the effectiveness and the safety of the techniques. Because unlike the industrial fields, the failure of the decommissioning technique in nuclear power plants can cause the spread or leakage of radioactive materials. In the「Regulation on Technical Standards for Nuclear Reactor Facilities, Etc.」is stated that the licensee shall apply proven technology to decommissioning and if the licensee apply new technology, he must provide resonable evidence and prove its safety. In accordance with this approach, Nuclear Safety and Security Commission (NSSC) Notice No. 2021-24 can be applied to the decommissioning technology as one of a technical standard related with the demonstration of it. And it states 9 kinds of elements related to the radioactive waste management facilites and components like the management of radioactive effluents, prevention of contamination and overflow by radioactive materials, etc. But, they are mixed with the radioactive material considerations and industrial considerations, and these considerations are usually for the facilities, not equipments or techniques. On the other hand, in the IAEA Safety Standards Series No. WS-G-2.1 Section 6.15 to 6.20, it recommended to evaluate 12 considerations for the decontamination technique and 7 considerations for the dismantling techniques. The Decommissioning Guide in Germany recommends to consider 3 conditions for radiation protection of decontamination techniques and 4 conditions for dismantling techniques. Therefore, it is necessary to compare the safety requirements or recommendations related to the demonstration of decommissioning technology with the other countries to check there is something to learn from it.

According to the second high-level radioactive waste management national basic plan announced in December 2021, the reference geological disposal concept for spent nuclear fuels (SNF) in Korea followed the Finnish concept based on KBS-3 type. Also, the basic plan required consideration of the development of the technical alternatives. Accordingly, Korea Atomic Energy Research Institute is conducting analyses of various alternative disposal concepts for spent nuclear fuels and is in the final selection stage of an alternative disposal concept. 10 disposal concepts including reference concept were considered for analysis in terms of disposal efficiency and safety. They were reference concept, mined deep borehole matrix, sub-seabed disposal, deep borehole disposal, multi-level disposal, space disposal, sub-sea bed disposal, long-term storage, deep horizontal borehole disposal, and ice-sheet disposal. Among them, first 4 concepts, mined deep borehole matrix, sub-seabed disposal, deep borehole disposal, multi-level disposal, were selected as candidate alternative disposal concepts by the evaluation of qualitative items. And then, by the evaluation of quantitative and qualitative items with specialists, multi-level disposal concept was being selected as a final alternative disposal concept. Design basis and performance requirements for designing alternative disposal systems were laid in the previous stage. Based on this, the design strategy and main design requirements were derived, and the engineered barrier system of a high-efficiency disposal concept was preliminary designed accordingly. In addition, as an alternative disposal concept, performance targets and related requirements were established to ensure that the high-efficiency repository system and its engineered barrier system components, such as disposal containers, buffer bentonites, and backfill perform the safety functions. Items that qualitatively describe safety functions, performance goals, and related requirements at this stage and items whose quantitative values are changed according to future test results will be determined and updated in the process of finalizing and specifically designing an alternative highefficiency disposal system.

As the first step of risk management, risk identification is inevitable to understand the degree of work safety. However, the safety requirements can be divided in necessary factors and additional factors. Thus, we propose a safety requirements assessment model using Kano model derived from Herzberg’s two-factor theory, classifying safety requirements into ideal elements and must-be elements. The Kano model is usually applied to evaluate customer satisfaction divided into three major requirements in the fields of product development and marketing: attractive, must-be, and one-dimensional requirements. Among them, attractive requirement and must-be requirement are matched with ideal element and must-be element for safety requirement classification, respectively. The ideal element is defined as preventive safety elements to make systems more safe and the must-be element is referred to as fatal elements to be essentially eliminated in systems. Also, coefficients of safety measurement and safety prevention are developed to classify different class of safety requirements. The positioning map is finally visualized in terms of both coefficients to compare the different features. Consequently, the proposed model enables safety managers to make a decision between safety measurement and prevention.

Modern weapon systems are getting more complex in terms of the functionality and also the conditions on the environment and range in which they are deployed and used. Therefore, many development programs can easily be exposed to a variety of risks, resulting in delayed schedules and cost overrun. As such, effective means are necessary to keep the defence budget at an affordable level while competitive edges on technological aspects are retained. As one way to meet those need, modeling and simulation (M&S) methods have widely been used, particularly in the test and evaluation (T&E) process for weapon systems development. The result of M&S-based systems development should be evaluated by the verification, validation & accreditation (VV&A) process to assure keeping reliability at a desired level. On the other hand, due to the explosiveness, the weapons systems development naturally requires to consider safety issues in both the T&E and operational periods. The purpose of this paper is to improve the VV&A process by reflecting the safety requirements therein. To do so, the VV&A process has been analyzed and graphically modeled first and then safety elements have been incorporated effectively. The use of the improved process in the war ships development has also been discussed. Based on the process proposed and the consequent database constructed, the target system can be expected to benefit from reducing development risks while assuring systems safety.

Modern systems can be characterized by ever-increasing complexity of both the functionality and system scale. Thus, due to the complexity the chances of accidents resulting from systems failure can then be growing. Even worse is that those accidents could result in disastrous damage to the human being and properties as well. Therefore, the need for the developed systems to be assured with systems safety is apparent in a variety of industries such as rail, automobiles, airplanes, ships, oil refinery, chemical production plants, and so on. To this end, in the industry an appropriate safety standard has been published for its own safety-assured products. One of the core activities included in the most safety standards is hazard analysis. A conventional approach to hazard analysis seems to depend upon the scenarios derived from the ones used previously in similar systems or based on former experience. The objective of this paper is to study an improved process for scenario-based hazard analysis. To achieve the goal, the top-level safety requirements have first been reflected in the scenarios. By analyzing and using them, the result has then lead to the development of safety-assured systems. The method of modeling and simulation has been adopted in the generation and verification of scenarios to check whether the safety requirements are reflected properly in the scenarios. Application of the study result in the case of rail safety assurance has also been discussed.

본 연구에서는 당직항해사의 해상상황 인식개선을 위해 시각적 항해보조 장비를 개발하고 그 성능시험 결과를 분석하였다. 개발된 장비는 Pan/ Tilt 내부에 고성능 카메라와 레이져 거리 측정기를 장착하고 있다. 개발된 장비를 선박에 장착하여 실선 실험을 수행함으로써 각 요소별 성능을 평가하였다. 이 결과를 바탕으로 개발 장비의 형식 승인을 위한 장비 환경 평가와 성능 평가 요소를 지정하였고 그에 대한 평가방법을 제시하였다.

Modern systems become more complex and the demand for systems safety goes up sharply. Thus, the proper handling of the safety requirements in the systems design is getting greatly increased attention these days. Hazard analysis has been one of the active areas of research in connection with systems safety. In this paper, we study a subject on how the hazard analysis results can be incorporated in the systems design. To this end we set up a goal on how to systematically generate safety requirements that should reflect hazard analysis results and be implemented in the systems design and development. To do so, we first review the process for systems design and suggest the associated Model. Then the process and results of hazard analysis are analyzed and Modeled particularly with emphasis on the safety data. The resulting data Model incorporating both the hazard analysis and system life cycle is used in the generation of safety requirements. Based on the developed data Model, the generation of the requirements, the construction of requirements DB, and the change management later on is demonstrated through the use of a computer-aided software tool.

It is becoming more and more important to develop safety-critical systems with special attention. Examples of the safety-critical systems include the mass transportation systems such as high speed trains, airplanes, ships and so forth. Safety critical issues can also exist in the development of atomic power plants that are attracting a great deal of attention recently as oil prices are sky-rocketing. Note that the safety-critical systems are in general large-scale and very complex for which case the effects of adopting the systems engineering (SE) approach has been quite phenomenal. Furthermore, safety-critical requirements should necessarily be realized in the design phase and be effectively maintained thereafter. In light of these comments, we have considered our approach to developing safety-critical systems to be based on the method combining the systems engineering and safety management processes. To do so, we have developed a design environment by constructing a whole life cycle model in two steps. In the first step, the integrated process model was developed by integrating the SE (ISO/IEC 15283) and systems safety (e.g., hazard analysis) activities and implemented in a computer-aided SE tool environment. The model was represented by three hierarchical levels: the life-cycle level, the process level, and the activity level. As a result, one can see from the model when and how the required SE and safety processes have to be carried out concurrently and iterately. Finally, the design environment was verified by the computer simulation.

It is well known that the test and evaluation plan (TEP) is very crucial in the successful development of safety-critical systems. As such, this paper discusses an approach to the development of the TEP for a system that should meet safety requirements in the systems development process. It is studied how to incorporate the result of preliminary hazard analysis (PHA) in generating the safety requirements. It is also discussed how to deal with them when the system requirements (i.e., functions, performance, constraints, components, etc) and the safety requirements are integrated into one model. While doing so, we have constructed the required traceability among them, which is necessary and very useful when the safety requirements need to be corrected or be changed. The use of the traceability makes it possible to easily check out whether and how the safety requirements are properly incorporated in the system design process. Furthermore, without the verified traceability, the system cannot be changed or upgraded later. In order to implement the model on a computer-aided tool, we have constructed a database (DB) schema. As a result, the implemented model/DB allows to automatically generate TEP which can be used to measure the performance and safety level of the developed system.

본 논문에서는 고준위폐기물 처분용기를 지하 심지층에 처분하기 위하여 요구되는 구조설계 요구조건과 구조안전성 평가 기준을 도출하였다. 고준위폐기물은 높은 열과 많은 방사능을 방출하기 때문에 고준위폐기물을 넣어 보관하는 처분용기는 그 취급에 많은 주의가 요구된다. 이를 위하여 고준위폐기물 처분용기는 장기간(보통 10,000년 동안) 안전한 장소에 보관되어야 한다. 보통 이 보관 장소는 지하 500m에 위치한다. 지하 깊은 화강암에 고준위폐기물을 보관하도록 설계되는 처분용기는 내부주철삽입물과 이를 감싸고 있는 부식에 강한 와곽쉘, 위 덮개와 아래 덮개로 구성되는 구조로 되어 있으며 지하수압과 벤토나이트 버퍼의 팽윤압을 받는다. 따라서 고준위폐기물 처분용기는 심지층에 보관 시 이들 외력들을 견디도록 설계되어야 한다. 만약에 발생 가능한 모든 하중조합을 고려한 처분용기 설계가 되지 않으면 심지층에 위험한 고준위폐기물 처분 시에 처분용기에 소성변형이나 크랙 또 좌굴같은 구조적 결함이 발생할 수 있다. 따라서 심지층에 처분용기를 처분 시에 처분용기에 발생하는 구조적 문제들이 발생하지 않게 하기 위하여 여러 가지 구조해석이 수행되어야 한다. 이러한 구조해석 수행에 앞서 처분용기 설계 타당성을 평가하기 위한 기준이 필요하다. 또한 평가기준에 영향을 미치는 설계요구조건(설계변수)이 명확히 검토되어야 한다. 따라서 본 논문에서는 처분용기의 구조설계 요구조건(설계변수)과 구조 안전성 평가기준을 도출하고자 한다.

In the era of digital technology, display device is the one of the important interface tool to communicate and transmit the information. Among the various display devices, CRT is the most popular one. Even though the CRT has many advantages comparing to other devices, it is faced to overcome its a few disadvantages especially in volume, shape and price, etc, In this paper, we try to show the development strategy of CRT corresponding with flat displays in the view point of ergonomics.