The Derived Concentration Guideline Level (DCGL) is required to release the facility from the nuclear safety act at the stage of site restoration of the decommissioning nuclear power plant. In order to evaluate DCGL, there are various requirements, and among them, the selection of input parameters based on the application scenario is the main task. Especially, it is important to select input parameters that reflect site characteristics, and at this time, a single deterministic value or a probabilistic distribution can be applied. If it is inappropriate to apply a particular single value, it may be reasonable to apply various distributions, and the RESRAD code provides for evaluation using probabilistic methods. Therefore, this study aims to analyze the difference between the application of the deterministic method and the application of the probabilistic method to the area and thickness of the contaminated zone among the site characteristics data. This study analyzed the thickness and area of the contaminated zone, and in the case of thickness, the deterministic method was applied by changing the thickness at regular intervals from the minimum depth considered by MARSSIM to the thickness of the unsaturated zone identified in previous research data. In addition, a probabilistic analysis was performed by applying a distribution to the thickness of contaminated zone. Second, for the area of the contaminated zone, the dose was evaluated for each area in consideration of the areas to be considered when deriving Area Factor (AF), and the resulting change in DCGL was observed. As a result, the DCGL tends to decrease as the thickness increases, and it seems to be saturated when the thickness exceeds a certain thickness. Therefore, It was confirmed that the level of saturated values is similar to that of entering a probabilistic distribution, and in the case of a parameter that is reasonable to enter as a distribution rather than as a single value, it is sufficiently conservative to perform a probabilistic evaluation. In the case of area change, the DCGL evaluation result showed that the DCGL increased as the scale decreased. The magnitude of the change varies depending on the characteristics of each radionuclide, and in the case of radionuclides where external exposure gamma rays have a major exposure effect, the change is relatively small. It can be seen that the change in DCGL according to the area has the same tendency as the AF applicable to the survey unit for small survey units applied in the final status survey.

Safety-related items in the decommissioning Nuclear Power Plants (NPPs) can largely consider safety for workers and residents. At this time, the effects of radioactive contamination on the Systems, Structures, and Components (SSCs) are caused by the performance of work related to Decontamination and Dismantlement (D&D) activities. Classification according to dismantling activities will be important, and the decay factor of radionuclides and the impact of contaminations due to plant characteristic (thermal and electrical capacity) in estimation of exposure dose from such activities will be considered compared to other overseas NPPs. Therefore, this study will consider some factors to consider for comparison with overseas cases in estimating worker exposure dose. To assess worker exposure doses, the classification of decommissioning activities must first be made. It should be classified including large components that can be generally considered, and the contents should be similar to compare with overseas cases. In case of decommissioned NPPs with prior experience, it is possible to predict worker’s exposure with respect to plant capacity, but this does not seem to have a specific correlation when reviewing the related data. Depending on the plant capacity, the occurrence of contamination of radioactive materials may have some correlation, but it cannot be determined that it has causality with the worker’s dose when dismantling. In addition, it is expected that the effects of workers’ exposure doses will vary depending on when the highly contaminated SSCs will be dismantled from permanent shut down. Therefore, the decay correlation coefficient for this high radiation dose works should be considered. If the high radiation dose work is performed before the base year, a correlation coefficient larger than 1 value will be applied, and in the opposite case, a value less than 1 will be applied. Whether or not to perform Full System Decontamination (FSD) is also an important consideration that affects worker dose, and correlation factors should be applied. In this study, the matters to be considered when estimating worker dose for dismantling NPPs were reviewed. This suggests factors to be reflected in the work classification and dose results for comparison with overseas NPP experiences. Therefore, when doing the workers’ dose estimation, it is necessary to derive a normalized doses considering each correlation factor when comparing with overseas cases along with dose estimation for the dismantling activities.

The nuclear power plant decommissioning project inevitably considers time, cost, safety, document, etc. as major management areas according to the PMBOK technique. Among them, document management, like all projects, will be an area that must be systematically managed for the purpose of information delivery and record maintenance. In Korea, where there is no experience in the decommissioning project yet, data management is systematically managed and maintained during construction and operation. However, if the decommissioning project is to be launched soon, it is necessary to prepare in consideration of the system in operation, what difference will occur from it in terms of data management, and how it should be managed. As a document that can occur in the decommissioning project, this study was considered from the perspective of the licensee. Therefore, the types of documents that can be considered at Level 1 can be divided into (1) corresponding documents, (2) project documents, (3) internal documents, and (4) reference materials. Four document types are recommended based on Level 1 for the classification of documents to be managed in the decommissioning of nuclear facilities. In this study, documents to be managed in the decommissioning project of nuclear facilities were reviewed and the type was to be derived. Although it was preliminary, it was largely classified into major categories 1, middle categories 2, and 3 levels, and documents that could occur in each field were proposed. As a result, it could be largely classified into corresponding documents, project documents, internal documents, and reference materials, and subsequent classifications could be derived. Documents that may occur in the decommissioning project must be managed by distinguishing between types to reduce the time for duplication or search, and the capacity of the storage can be efficiently managed. Therefore, it is hoped that the document types considered in this study will be used as reference materials for the decommissioning project and develop into a more systematic structure.

The domestic Nuclear Power Plant (NPP) decommissioning project is expected to be carried out sequentially, starting with Kori Unit 1. As a license holder, in order to smoothly operate a new decommissioning project, a process in terms of project management must be well established. Therefore, this study will discuss what factors should be considered in establishing the process of decommissioning NPPs. Various standards have been proposed as project management tools on how to express the business process in writing and in what aspects to describe it. Representatively, PMBOK, ISO 21500, and PRICE 2 may be considered. It will be necessary to consider IAEA safety standards in the nuclear decommissioning project. GSR part 6 and part 2 can be considered as two major requirements. GSR part 6 presents a total of 15 requirements, including decommissioning plans, general safety requirements until execution and termination. GSR part 2 presents basic principles for securing the safety of nuclear facilities, and there are a total of 14 requirements. Domestic regulatory guidelines should be considered, and there will be largely laws and regulations related to the decommissioning of nuclear facilities, guidelines for regulatory agencies, and guidelines and regulations related to HSE. The Nuclear Safety Act, Enforcement Decree, Enforcement Rules, and NSSC should be considered in the applicable law for nuclear facilities. Since the construction and operation process has been established for domestic decommissioning project, there will be parts where existing procedures must be applied in terms of life cycle management of facilities and the same performance entity. As a management areas classification in the construction and operation stage, it seems that a classification similar to Level 1 and Level 2 should be applied to the decommissioning project. This study analyzed the factors to be considered in the management system in preparing for the first decommissioning project in Korea. Since it is project management, it is necessary to establish a system by referring to international standards, and it is suggested that domestic regulatory reflection, existing business procedures, and domestic business conditions should be considered.

The goal of the decommissioning of nuclear facilities is to remove the regulations from the Nuclear Safety Act. The media that can be considered at the time of remediation stage may usually include soils, buildings, and underground materials. In addition, underground materials may largely be the groundwater, buried pipes, and concrete structures. In fact, it can be seen that calculations of the Derived Concentration Guideline Level (DCGL) and ALARA action levels was conducted in the case of overseas decommissioning experiences of Nuclear Power Plants (NPPs). Therefore, the aim of this study is to review the remediation activities and scenarios applied for the calculation of ALARA action level from the overseas decommissioned nuclear power plants. Media that can be considered for DCGL calculation at the time of license termination may differ from site to site. If the DCGL for the target media was derived, whether additional remediation actions are required under the DCGL value from the ALARA perspective was identified by calculating the ALARA action levels in the case of the U.S. The activities to determine whether additional clean-up is justified under the regulatory criteria are remediation actions which is dependent on the material contaminated. Therefore, the typical materials that can be subjected to remediation are soils and structure basements in the overseas cases. Remediation actions involved in the decommissioning process on the structure surfaces can be typically considered to be scabbling, shaving, needle guns, chipping, sponge and abrasive blasting, pressure washing, washing and wiping, grit blasting, and removal of contaminated concrete. For the cost-benefit analysis of the media subject to DCGL calculation, it is necessary to assume a scenario for the remediation actions of the target media. The scenarios can be largely divided into two types. Those are basement fill and building occupancy scenario. In basement fill mode, buildings and structures on the site are removed, and the effect of receptors from the contamination of the remaining structures is considered. In the building occupancy mode, it is assumed that the standing building remains on the site after the remediation stage. It is a situation to evaluate how the effect of additional remediation actions changes as the receptors occupy inside of the contaminated building. Therefore, parameters such as population density, area being evaluated, monetary discount rate, numbers of years, etc. can be set and assessed according to the scenarios.

The establishment of processes for the decommissioning a Nuclear Power Plant (NPP) is one of the objects that must be prepared in carrying out the decommissioning project. In particular, in the domestic situation, where there is no experience of decommissioning commercial NPPs, it is necessary to organize the tasks and contents well in advance for the successful initiation of the project. Therefore, this study intends to present a guide-level approach to develop management for domestic decommissioning projects. As a documented template for recognizing a process, there may be a process map and description, and information such as the work structure and the relations between the activities should be indicated. In reality, activities will be managed through a set of computer system, so it would be better if the work content, activity flow, relation, management target information, computerization contents, etc. were materialized in the process. What is important here is to define the management areas and activities and draw the activity flow. Domestically, it has rich experience in construction of NPPs and has a track record of exporting NPPs to the UAE. From these experiences, we have established a framework for standardized work in construction management and construction processes, and are performing them through a computerized system. Since the work of decommissioning has a similar nature to that of construction, we will be able to benchmark the procedure for the decommissioning from the construction management procedures. Typically, in the case of schedule management, the concept and structure of the construction process will be applicable to the decommissioning. Meanwhile, the licensee of domestic decommissioning is the same as the licensee that performs the operation, and the members who will perform the decommissioning also have experience working in the operation period. Therefore, the decommissioning works are an extension of the task during operation. Representatively, there are some processes that can be applied as it is even when decommissioning, such as dismantling work and the safety management process of the radiation zone. Therefore, in carrying out the decommissioning of NPPs in Korea, processes and activities of the management area should be established from the construction processes with abundant experience and the processes during operation. Rather than making a completely new work process, this approach that properly reflects the existing work flow is expected to be an appropriate way to avoid the repulsion of employees and maladjustment to the new environment.

한국의 가장 오래된 상업 원전인 고리 1호기가 2017년에 해체가 이루어질 예정이다. 원전 해체 폐기물의 적절한 처리는 효율적인 원전해체에 있어 중요한 역할을 할 것이다. 특히, 저준위 또는 오염되지 않은 금속폐기물의 재활용은 폐기물 발생 저감은 물론 처분장의 공간을 절약하는데 기여할 것이다. 본 논문은 재활용 시스템의 개념설계와 정의된 업무 흐름에서 발생 하는 피폭 선량을 평가하는데 그 목적이 있다. 작업의 흐름과 운전 개념을 정립하기 위해 다양한 형태의 다이어그램을 설계 하였다. 선량평가에 필요한 시나리오는 개념설계를 기반으로 선정되었으며, RESRAD-RECYCLE을 이용하여 선량을 평가하였다. 이를 통하여, 결정적 시나리오 선별, 핵종 특성 및 핵종 분배가 선량에 미치는 영향을 분석하였다. 더 나아가, 선량분석은 피폭 시나리오에 대한 대체 방안 수립, 필요한 제염 및 방사선방어 프로세스 그리고 허용 방사능 검토의 정보를 제공 하는데 사용 될 수 있을 것이다.

Nanoparticles are widely used in various fields such as electronics, medicines and getting focus on the application in food industry for developing intelligent delivery system with bioactive ingredients or functional nutrients. Basic study on possible toxicological effect of food applicable nanoparticles is required for a practical application in food industry. In this study, size-controlled bovine serum albumin (BSA) nanoparticles were prepared by a desolvation method and their cytotoxicity was investigated. BSA nanoparticles were prepared with mean diameters as 115, 137, 159, and 299 nm, then cytotoxicity was evaluated with RAW 264.7 macrophages as in vitro model. Cell viabilities were significantly affected as increasing nanoparticle concentration. Smaller the sizes of nanoparticles, LD50 values were significantly reduced. LD50 values of BSA nanoparticles were 50, 65, 126, and 170 μg/ml, respectively. Nanoparticle was supposed to induce the apoptosis of RAW 264.7 marcrophages and underlying mechanism will be investigated in future. These findings will be used as valuable basement for nanofood development with BSA nanoparticles.

정보기술 발전과 함께 스마트폰이나 태블릿PC와 같은 터치스크린 기반의 다양한 휴대용 디바이스가 보급 및 활용되고 있다. 이러한 스마트 기기들은 탭(tab)이나 핀치(pinch)와 같은 단순하고 직관적인 터치 제스처를 활용하고 있다. 본 연구에서는 스마트기기 사용자의 지도 애플리케이션에 대한 접근성 및 편의성을 증대시킬 수 있는 제스처 라이브러리를 구현하여 터치 제스처, 에어 제스처, 조이스틱 제스처 등이 웹지도 제어에 사용하도록 하였다. 이러한 제스처 라이브러리의 가용성 평가를 위하여 프로토타 입 애플리케이션을 제작하여 다양한 제스처 인터페이스의 동작이 원활함을 확인하였다. 본 연구에서 구현한 제스처 라이브러리는 개발자가 사용하기에 편리한 형태의 객체 및 함수로 구성되었기 때문에, 웹지도와의 연동만으로도 다양한 제스처 인터페이스를 갖춘 지도 애플리케이션을 개발할 수 있다. 또한 현재까지 지도 인터페이스로서는 제안되지 않은 형태의 다양한 제스처 기능을 포함하고 있으며, 향후 HTML5 기반으로 확장하여 모바일 운영체제 비의존적인 라이브러리로 기능할 수 있을 것이라 사료된다.

최근 항시적 광역 모니터링이 가능한 위성원격탐사 기술에 의해 산불감시의 효율성이 증대될 것으로 기대되고 있는 가운데, 미국의 Terra, Aqua, GOES (Geostationary Operational Environmental Satellite), 유럽연합의 Meteosat, 그리고 우리나라의천리안위성 및 후속위성도 산불정보의 실시간 제공을 목표로 하고 있다. 본 연구에서는 이러한 위성기반 산불정보를 대민서비스하기 위한 방법의 일환으로 스마트폰 앱을 구현하여, 북한지역을 포함한 한반도 전역의 위성자료로부터 추출한 산불발생여부, 산불탐지 신뢰도, 산불의 방사강도 등의 정보를 DBMS (Database Management System)에서 관리하고, 안드로이드와 iOS 스마트폰을통해 제공하는 서비스의 원형을 개발하였다. 공통적 핵심기능은 HTML5 (HyperText Markup Language 5) 웹페이지로 구성함으로써 상이한 OS (Operating System)의 네이티브 앱과 결합하는 하이브리드 방식을 통해 소스코드의 재사용성과 시스템 확장성을 추구하였으며, 일자별 산불조회, 최근 산불조회, 주변 산불조회 등의 기능을 포함하도록 하였다. 현재는 위성기반 산불탐지 자료가 실시간 제공되지 않아 산불발생의 이력정보를 서비스하도록 구성하였지만, 2010년대 후반 우리나라 기상위성의 산불탐지 자료가 실시간으로 제공될 것이므로, 정부 3.0의 정보공개 흐름과 함께 국민 모두에게 필요한 실시간 산불정보 조회가 가능해질 것으로 예상된다. 본 연구는 위성기반의 실시간 산불정보 앱 개발을 위한 출발점으로서 의의를 가지며, 향후 산불정보 앱은 SNS (SocialNetworking Service) 기반의 빅데이터 마이닝 기술과 연동하는 통합 솔루션으로 구성되어야 그 활용성이 보다 더 제고될 것이다.

오늘날의 웹 GIS(geographic information system)에서는 다양한 원격지로부터 접근하는 사용자를 위하여 대용량 시계열 자료를 효과적으로 관리 및 공유할 수 있는 방법론을 필요로 한다. 이 논문에서는 시계열 래스터 데이터베이스의 웹 서비스를 위하여 REST(Representation State Transfer) 방식의 오픈 API를 구현함으로써 웹 GIS 서비스의 상호운용성과 확장성을 향상시키는 방안을 제시하고자 한다. 먼저 DBMS(database management system) 내에 시간객체 및 시간함수를 생성하여, 이미 존재하는 공간객체 및 공간함수와 결합시킴으로써 시계열 래스터 자료에 대한 시공간연산이 가능하도록 하였다. 또한 사용자와 서버 간의 요청/응답 구조를 경량화한 REST 방식의 데이터 통신을 채택하고, 그 인터페이스인 URI(unified resource identifier)를 통해 시공간 질의문 구성이 가능하도록 하였다. 이러한 오픈 API는 개발 클라이언트의 환경에 상관없이 동일한 방식으로 사용될 수 있으며, Java, C++.NET, C#.NET, VB.NET 등의 컴파일러 언어와 JavaScript, Python, Ruby, R 등의 스크립트 언어를 포함하여 HTTP(Hypertext Transfer Protocol)를 사용하는 모든 프로그래밍 언어가 지원된다. 본 연구에서 구현한 오픈 API의 가용성 테스트를 위하여, 웹상에서 3D 디스플레이를 지원하는 구글어스 웹플러그인(Google Earth Web Plugin)과 WebGL(Web Graphics Library) 을 이용하여 시계열 래스터 자료에 대한 시공간 질의와 그 결과의 3차원 시각화를 수행하였다.

FOSS(free and open source software)는 라이선스의 제약 없이 자유롭게 소스코드를 재사용하거나 수정 및 배포할 수 있는 소프트웨어로서, 정보시스템 구축의 새로운 대안으로 자리잡아가고 있다. 최근 GIS의 컴퓨팅 환경이 웹으로 확장되면서 FOSS를 활용하여 공간데이터를 공유하거나 시각화하기 위한 시도들이 이루어지고 있다. 기존의 연구들을 통해 볼 때, 웹GIS에서 FOSS 애플리케이션들은 환경 및 생태 정보 제공을 위한 지도서비스가 주를 이루며 분석지향적인 사례는 매우 드물다. 또한 공간 DBMS(database management system), GIS툴, 통계패키지 등의 FOSS가 개별적으로 웹GIS에 활용되어 왔으나, 개방성과 재사용성이 우수한 이들 FOSS를 커플링(coupling)하면 공간자료의 공유, 시각화에서 더 나아가 공간데이터의 통계분석을 지원하는 웹GIS가 구축 가능할 것이다. 이에 본 연구에서는 웹 환경에서 DBMS, GIS툴 및 통계패키지를 커플링하는 브로커리지(brokerage) 모듈을 개발하고, 이를 이용하여 공간자료의 저장, 질의, 처리 및 통계분석을 수행하며 그 결과를 시각화하는 FOSS 기반의 웹GIS 프레임워크를 제시하고자 한다. 공간 DBMS로는 래스터와 벡터가 모두 지원되는 PostGIS을 이용하였고, 공간데이터 프로세싱에는 GRASS, 통계분석에는 R, 시각화를 위한 지오브라우저로는 Google Maps와 Google Earth를 사용하였다. 이러한 FOSS들의 커플링을 위한 브로커리지 모듈은 운영체제 독립적인 Java 언어로 구현되었으며, API(application programming interface)를 통해 JSP(Java Server Pages)에서 참조하여 웹 인터페이스를 구성하도록 하였다. 본 시스템에 대한 테스트에서는, 남한지역의 NDVI(normalized difference vegetation index)와 환경요소 간의 회귀분석을 수행하는 프로토타입을 통해 공간데이터의 공유, 프로세싱, 시각화, 분석에 있어서의 가용성이 검토되었다.