본 연구에서는 최근 발표된 가이아 자료를 이용하여 늙은 산개성단 M67의 운동학적 연구 결과를 발표하고자 한다. 사전 연구에서 선정한 934개 별들의 분포로부터 성단의 크기 및 구조를 조사하였다. M67의 투영된 중심거리에 따른 구성원의 표면 밀도 분포를 통해 성단 겉보기 반지름과 구성원의 50%를 포함하는 반지름(half-number radius, rh) 을 각각 약 30′(7.6 pc) 및 12.′4(3.1 pc)으로 결정하였다. 또한 이 분포를 King의 밀도 모형에 맞추어 성단 중심부 반지름(core radius, rc) 4.′0(1.0 pc)을 얻었다. 성단의 색-등급도를 등연령 곡선과 비교하여 나이를 약 4 0억 년으로 추정하였 고, 이는 이전 연구의 결과들과 잘 일치한다. 성단 구성원들의 상대적인 고유운동을 조사한 결과, rh보다 안쪽에 위치한 구성원의 고유운동 방향은 등방하게 나타나는 반면, 외곽에 있는 별들은 성단 중심 방향으로 운동하고 있는 것으로 나 타났다. 이것은 성단의 외곽이 수축하고 있다는 것을 의미한다. rc 이내에 분포하는 별들의 시선속도를 분석한 결과, 천 구 상에서 동-서 방향(위치각 100o-280o)으로 놓여있는 축을 중심으로 성단이 회전 하고 있음을 발견하였다. 이것은 성 단의 형성 이후에도 오랜 시간 동안 성단의 회전이 지속될 수 있음을 의미한다. M67이 비리얼 평형 상태에 있다고 가 정하여 계산한 운동학적 질량은 약 1600 M⊙이다. M67의 동역학적 이완시간은 약 1.9억 년 정도로 예상되며 이것은 성단의 나이인 4 0억 년보다 짧다. 그러므로 이 성단은 동역학적으로 이완된 상태라고 할 수 있다. 실제로 성단 중심으 로부터 거리에 따른 별들이 평균 질량이 작아지는 질량분리 현상을 확인하였다.

The decommissioning of a nuclear power plant is a project that consists of several stages, and various technologies are applied when performing various tasks at each stage. And it is essential to secure safety and economic feasibility. As the paradigm has changed due to digital transformation in various industries, digitalization is applied to the life cycle of nuclear power plant from construction, operation and decommissioning project. Element technologies are being developed for decommissioning plan establishment, process design, econtamination method, decommissioning work process, waste management, environmental monitoring and radiation dose simulation. The utilization of digital twin in the decommissioning stage is classified into three categories. ① Process Monitoring (decommissioning work procedure, work progress (plan/actual), real-time work status and etc.) ② Facility Monitoring (real-time sensing and video data monitoring, decommissioning SSCs information, work alarm and etc.) ③ Safety Monitoring (work safety, radiation exposure, fire monitoring, work risk and etc.) A system suitable for the decommissioning stage and work should be developed in consideration of the target of use, development function, and when to create data according to the purpose of the system. Simulation module according to user purpose should be provided. In addition, data-base management should be performed according to the decommissioning characteristics in consideration of the data associated with the existing operating system. The system to be developed should support the project management to comply with the domestic standards and regulations to be determined in the future. This will improve the competitiveness of domestic and foreign markets.

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.

Trojan Nuclear Power Plant (NPP), a four-loop PWR designed by Westinghouse and owned by Portland General Electric (PGE), reached its initial threshold in 1975 and was operational until November 1992. PGE received a Possession Only License from the NRC in May 1993. In 1995, limited decommissioning activities began at the Trojan, including the completion of a large components removal project to remove and dispose of four steam generators and pressurizers from the containment building. In April 1996, the NRC approved a plan to dismantling the Trojan NPP and began more aggressive component removal activities. At the end of 1998, part of the radioactive drainage system began to be removed, and embedded piping decontamination and survey activities began. Trojan NPP has more than 8,840 m of contaminated pipelines throughout the power block. Most of Trojan NPP’s contaminated embedded piping can generally be divided into four categories drainage piping, ventilation ducts, buried process piping, and other items. For the Trojan NPP, the complete removal of contaminated and embedded piping without damaging the building would have significantly increased costs due to the structural considerations of the building and the depth of the embedded pipe. Therefore, Trojan NPP has chosen to conduct the Embedded Pipe Remediation Project (EPRP) to clean and in situ survey of most of the embedded piping to meet the Final Site Survey (FSS) acceptance criteria, with much success. This study provides a discussion of EPRP activities in the Trojan NPP, including classification and characterization of affected piping, modeling of proposed contamination acceptance criteria, and evaluation of various decontamination and survey techniques. It describes the decontamination tools, techniques, and survey equipment and the condition of work and cost estimate costs used in these projects. To identify embedded piping and drains at the Trojan NPP, based on frequent site surveys, plan sketches showing an overview of system flow paths and connections and database were developed to identify drain inputs and headers. This approach effort has been a successful method of remediation and site survey activities. The developed database was a valuable asset to the EPRP and a Work Breakdown Structure (WBS) code was assigned to each drains and headers, allowing the embedded piping to be integrated into the decommissioning cost estimation software (Decon. Expert) and schedule, which aided in decommissioning cost estimation. Also, regular database updates made it easy to check the status of the decommissioning project data. The waste system drain at Trojan NPP was heavily contaminated. The goal of the remediation effort is to completely remove all removable contamination and to reduce the fixed contamination below the decided contamination acceptance criteria. Accordingly, Hydrolysis, Media blast, Chemical decontamination and Pipe removal were considered as remediation option. Trojan NPP’s drainage pipe decontamination option did not cause a significant corrosion layer inside the pipe and media blast was chosen as the main method for stainless steel pipe. In particular, the decommissioning owner decontaminates most of the embedded piping in-situ to meet the FSS acceptance criteria for economic feasibility in Trojan NPP. The remaining pipe was filled with grout to prevent leaching and spreading of contamination inside the pipe. In-situ decontamination and survey of most of these contaminated pipes are considered the most cost-effective option.

The decommissioning project of NPP is a large-scale project, with various risks. Successful implementation of the project requires appropriate identification and management of risks. IAEA considered risk management “To maximize opportunities and to minimize threats by providing a framework to control risk at all levels in the organization”. Framework-based risk management allows project managers to identify key areas in which action should be taken at an appropriate time. Also, it enables effective management of projects by supporting decision-making on sub-uncertainty. Risk could be categorized according to the source of the risk. This is called Risk Breakdown Structure (RBS), and is documented as a risk assumption register through a risk identification process. IAEA considers various factors when defining risks in accordance with ISO 31000:2009. IAEA SRS No.97 presents a recommended risk management methodology for the strategy and execution stage of the decommissioning project of nuclear facilities through the DRiMa project conducted from 2012 to 2015. The risk breakdown structure classified in DRiMa project is as follows: (1) Initial condition of facility, (2) End state of decommissioning project, (3) Management of waste and materials, (4) Organization and human resources, (5) Finance, (6) Interfaces with contractors and suppliers, (7) Strategy and technology, (8) Legal and regulatory framework, (9) Safety, and (10) Interested parties. They have various prompts for each category. Such a strategy for dealing with risks has negative risks (threats) or positive risks (opportunities). The negative risks are as shown in avoid, transfer, mitigate and accept. On the other side, the positive risks are as shown in exploit, share, enhance and accept. During the decommissioning, a contingency infrastructure is needed to decrease the probability of unexpected events caused by negative risks. The contingency infrastructure of decommissioning project includes organization, funding, planning, legislation & regulations, information, training, stakeholder involvement, and modifications to existing programs. Since all nuclear facilities have different environmental, physical or contamination conditions, risks and treatment strategies should also be applied differently. This risk management process is expected to proceed at the stage of establishing and implementing a detailed plan for the decommissioning project of each individual plant.

본 연구에서는 국제 전략적 제휴에서 파트너 간 문화적 거리가 점진적 혁신 성과와 급진적 혁신 성과에 미치는 효과에 대해 분석하고자 하였다. 이에 더하여, 동일 산업 간 제휴 및 이종 산업 간 제휴의 차이로 대표되는 파트너 간 산업 지식 기반의 차이가 독립변수의 효과를 조절하는지 규명해 보고자 하였다. 구체적으로, 문화 차이에서 비롯된 파트너 간 인지적 거리(recognition distance)가 혁신에 필요한 학습 능력에 영향을 미친다는 이론적 논의와 이러한 영향력이 산업 환경의 지식 기반 차이에 따라 달라진다는 관점 하에 가설을 설정하였다. 본 연구의 가설 검증을 위해서는 2009년부터 2012년까지 4년의 기간 동안 139개의 국내 코스닥 상장 기업이 체결한 364건의 국제 전략적 제휴를 표본으로 특허 창출 건수를 종속변수로 하는 음이항 회귀분석(negative binomial regression)을 실시하였다. 분석 결과, 제휴 파트너와의 문화적 거리가 멀수록 점진적 혁신에 긍정적 영향을 미치는 반면, 급진적 혁신에는 부정적 영향을 미치는 것을 확인할 수 있었다.