본 연구는 교정시설 내 교정치료공동체를 도입하여 마약류에 관한 법률 위반 수형 자들이 건강한 사회인으로 기능하여 재범을 예방할 수 있도록 교정차원에서 전문적인 치료와 치유를 제공하고자 하였다. 그래서 국외 교정치료공동체에 관한 질적연구를 체계적으로 분석하여 우리나라 교정치료공동체의 철학과 모듈 마련을 위한 기초 자료 로 활용하고자 질적 메타 종합 연구하였다. 현재 마약류에 관한 법률 위반 수형자들은 마약과의 전쟁을 선포한 이후 처벌받은 인원이 증가하고 있다. 현 정부에서는 증가하 는 마약류 수형자의 재범과 마약류 중독을 예방하고자 마약류 사용에 관한 법률위반 자를 구속과 처벌이 원칙인 형행이념으로 일관하고 있다. 하지만, 사회 전반에 확산되 고 있는 마약류 중독을 예방하지 못하고 있기에 마약류 수형자 관리에 대한 교정이념 의 변화에 대한 필요성이 대두되고 있다고 판단된다. 우리나라에서는 일부 교정시설 에서는 교정치료공동체를 실시하고 있지만, 교정치료공동체의 철학과 모듈이 미미하다. 그래서 본 연구에서는 국외 질적연구를 분석하여 우리나라에 맞는 교정치료공동 체 철학과 모듈의 기초 자료를 마련하고자 한다. 연구자는 구글 학술검색을 통하여 해 외에서 수행된 8편의 교정치료공동체 관련 질적 연구물들을 수집하였다. 수집된 질적 연구들은 Lguirre와 Bolton 제시된 질적 해석적 메타 종합 연구로 접근하여 분석하 였다. 자료 분석은 1차 문헌을 상세히 분석하면서 주제를 구성하였고, 2차 통합주제, 핵심 주제로 나눠 분석하여 주제를 구성하여 제시하였다. 해석적 이해를 중심으로 참 여자의 경험 중 교정치료공동체의 구조와 내용을 구체적인 분석으로 기술하였다. 분 석한 결과를 교정치료공동체의 성장 효과를 저해하는 부정적 요인과 긍정적인 요인으 로 나눠 기술하였다. 교정치료공동체의 부정적 요인은 생명력 없는 프로그램, 관행적 실천, 상호신뢰 기반의 동요로 나타났다. 긍정적 요인은 사회로 가는 디딤돌, 치료 집 중구조, 서로에게 배움, 인격의 재구조와 윤리적 인간으로의 진화, 자기주도적 단약 효능감 생성, 인본주의 치료 공간으로 나타났다. 본 연구의 의의는 교정치료공동체의 철학과 구성 방안을 제시한 연구로 마약류 수형자의 관리에 관한 교정정책차원에서 교정이념의 변화를 이루고자 하였다. 또한, 향후 교정기관에서 교정치료공동체의 도입 및 치료 처우에 교정치료공동체의 방향을 제시함으로 마약류 수형자의 재범 예방과 국민건강에 교정 연구의 학문 분야 발전에 크게 기여할 것으로 전망한다.

The objectives of this study is to classify evacuation types, derive the characteristics of 4 types, develop and discover evacuation routes within the performance hall space, and present the statistical classification results of the evacuation classification model by classification type. To achieve this purpose, the characteristics of each evacuation type's four types are applied through a network reliability analysis method and utilized for institutional improvement and policy. This study applies for the building law, evacuation and relief safety standards when establishing a performance hall safety management plan, and reflects it in safety-related laws, safety standards, and policy systems. Statistical data by evacuation type were analyzed, and measurement characteristics were compared and analyzed by evacuation types. Evaluate the morphological similarity and reliability of evacuation types according to door width and passage length and propose the install position of evacuation guidance sign boards. The results of this study are expected to be used as basic data to provide operation strategies for safety facility evacuation information sign boards according to evacuation route classification types when taking a safety management plan. The operation strategy for the evacuation sign boards installation that integrates employee guidance and safety training is applied to the performance hall safety management plan. It will contribute to establishing an operational strategy for performance space safety when constructing performance facilities in the future.

Considering the difficulties of the manufacturing industry by improving production efficiency in the era of high wages and aging in domestic automation facilities, automation facilities are considered an irreversible trend, but many serious related disasters are occurring due to the problems of increasing automation facilities due to the enlargement of manufacturing processes, line-up, and automation. The purpose of this study is to review the usage conditions and safety measures for industrial robots that are experiencing serious industrial accidents and are expected to continue to increase in facilities among automation facilities at the automation industrial site and propose ways to ensure the fundamental safety of the facilities at all times The suggestions are as follows. The purpose is to prevent safety accidents in advance by applying safety door aids to industrial sites and installing additional safety devices in safety slide door lock systems applied to safety fence doors of new and already installed facilities to detach safety keys and ensure that workers carry them at all times.

본 연구에서는 보육시설 내 식수인원 및 조리 종사자 근무현황에 따른 급식소 위생 관리수준을 평가하였다. 2021 년부터 2022년까지 풀무원푸드머스를 통해 식자재를 공급 받는 전국 199개 보육시설을 대상으로 61개 점검문항 중 평가결과에서 유의미한 일부 분석결과를 바탕으로 작성하 였다. 분석결과 식수인원이 적고, 조리 종사자가 적을수록 검수기록이 미 실시(P<0.05)되는 평가되었으며, 식수인원 이 적을수록 조리 종사자의 건강상태 확인이 미흡하고, 조 리 종사자가 적을수록 복장착용(P<0.05)이 미흡하였다. 또 한, 식수인원이 적은 보육시설일수록 소비기한 경과 식재 료 보관이 확인(P<0.05)되는 빈도 수가 높아 관리가 요구 되었으며, 가열조리 시 심부온도 측정기록은 미 실시(P<0.05) 되는 것으로 확인되었다. 그리고 식수인원이 적은 보육시 설일수록 조리시설의 유지관리가 미흡(P<0.05)하였다. ATP 측정결과에서는 식수인원이 적은 조리시설 종사자의 손과 도마에서 유의적으로 높은 ATP 수치가 검출(P<0.05)되었으 며, 조리종사자가 적을수록 근무 급식소의 도마에서 높은 ATP 수치(P<0.05)가 측정되었다. 분석결과를 종합해 볼 때 식수인원이 적은 보육시설일수록 조리운영을 위한 시설기반 관리가 부족하고, 위생관리가 미흡한 것으로 확인되었다. 따 라서 본 연구결과를 통해 식수인원 및 조리 종사자 수에 따 른 보육시설 급식소의 위생 관리수준을 판단하였으며, 향후 보육시설에 대한 국가 지원사업 선정 시 해당 연구결과가 기초자료로써 활용될 수 있을 것으로 사료된다.

In this paper, a tidal power conversion system (PCS) using seawater level differences was presented.. To verify the presented PCS, an actual lab-scale tidal power generation system was constructed. The operation of the lab-scale PCS was first modeled mathematically and was analyzed through dynamic simulation and experimental tests.

「장애인복지법」에 따라 국가 자격시험은 장애인과 비장애인이 동일한 시험에 응시할 수 있도록 하고 있으며, 청각장애는 동 력수상레저기구 면허취득 결격사유에 해당하지 않아 청각장애인도 면허취득을 할 수 있다. 선박이나 동력수상레저기구에서는 해상에서 충돌위험이 있을 때 조종신호, 경고신호 등의 위험신호를 음향신호를 통해 상대에게 알려 주위의 위험 상황을 발견하지 못하여 발생할 수 있는 사고를 예방하도록 하고 있다. 하지만, 청각장애인의 레저활동 중 주위 선박이나 동력수상레저기구의 소리를 통한 위험신호를 청 각장애로 인해 위험신호를 확인하지 못해 발생할 수 있는 해양사고를 방지할 수 있는 방안이 필요하다. 음향수신장치(Sound Reception System)는 선교가 완전히 폐위된 선박에 설치하여 외부 소리의 증폭과 소리의 수신 방향을 화면상에 표시하는 장치로서, 청각장애인의 동 력수상레저기구에 선박 음향수신장치를 활용하여 청각장애로 인해 청취할 수 없는 위험신호와 같은 음향신호의 유무 및 방향을 동력수 상레저기구의 화면상에 시각적 표시를 통해, 청각장애인의 레저활동 중 음향신호를 확인하지 못하여 발생할 수 있는 해양사고를 예방하 기 위한 개선방안을 제시하였다.

과거 감시와 통제, 박탈의 역할을 담당했던 교정시절은 보안성에 중점을 두어 설계되었다. 책임형벌주 의에 따른 자유박탈처분은 불가결한 것이지만 현대의 행형이념이 재소자의 재사회에 있다는 점, 구금 으로 인해 발생하는 재소자들의 정신, 심리적 문제 등이 적지 않다는 점 등으로 교정시설의 처우개선을 위한 논의가 진행되고 있다. 이에 본 연구는 교정시설 공간에서의 일상성 회복과 치유를 통한 재소자의 재사회화와 회복적 개념의 교정시설 설계를 제안하였다. 대상지에 대한 일성상 회복의 개념을 적용한 외부공간 설계의 구체적인 설계 전략은 다음과 같다. 첫째, 회복과 치유를 위한 6가지의 원칙을 적용하 였다. 물리적으로 안전하고 사고의 위험 요소가 없는 환경, 긍정적 교류의 장으로서의 환경, 차분한 분 위기의 환경, 이동과 선택의 자유가 보장되는 환경, 일상적 환경과 닮은 공간, 교정시설의 느낌이 사라 진 환경 등이다. 둘째, 연결에 중점을 둔 동선 체계화로 재소자와 자연환경의 상호작용을 촉진하였다. 셋째, 절화정원 조성을 통한 외부 사회와의 소통, 인간적인 연결, 일상성 회복과 치유의 조화를 모색하 였다. 본 연구는 교정시설에 대한 일상성 회복 개념의 적용 논의를 확장하고 앞으로 회복적 개념의 교정 시설 설계를 위한 참고 자료를 제공하는데 학술적 의의가 있다.

본 연구는 일반농산어촌개발사업의 사업내용 중 하나인 농촌중심지활성화사업으로 준공에 이른 농촌 커뮤니티 시설의 주민조직 직접 운영에 따른 운영성과와 농촌 커뮤니티 시설에 미치는 영향요인을 분석 하여 문제점을 도출하고 개선방안을 제시하는데 목적을 두고 있다. 또한 전라북도 농촌중심지활성화사 업으로 준공에 이른 농촌 커뮤니티 시설 중 주민조직에 의해 운영되고 예산이 비슷하며, 비교가 가능한 부안군 보안면, 김제시 금구면, 임실군 강진면을 대상으로 연구를 진행하였다. 설문지는 배포 후 회수하는 방법으로 수집하였으며, 일반현황과 독립변수의 측정지표에 근거한 리커트 7점 척도를 통해 분석한 결과는 다음과 같다. 설문결과는 설문에 대한 응답자의 일반현황, 빈도, 백분율 분석, 측정 문항의 신뢰 도 분석을 위해 크론바흐의 알파 값 계수법 분석, 세부 측정지표별 설문조사 분석, 연구가설 검증을 위한 다중회귀분석, 세부 운영성과의 차이를 분석하기 위한 일원배치 분산분석과 사후검정을 실시하였다. 연구가설과 리커트 7점 척도를 통한 연구의 결론은 측정문항의 신뢰성이 인정되었으며, 농촌 커뮤니티 시설의 주민조직 직접 운영은 시설의 운영성과에 영향을 미치고 있다. 성공적인 운영과 운영성과를 제 고 및 개선하기 위해서는 다양한 계층들의 이용에 있어 편리하도록 환경관리 및 시설의 설비에 최선의 노력을 기울여야 한다. 또한 시설 운영의 주체인 주민조직의 기능을 강화하여 지역의 공동체 교류공간 이 되도록 주민조직과 지역주민이 직접 관심을 가지고 참여하여 주민조직만의 공간을 확보하는 것이 중요하다. 이 연구를 통해 시설의 편리성과 개발의 유연성을 유지하여 다양한 계층의 주민들이 이용함 으로써 운영성과를 높일 수 있는 요인이 된다. 다양한 운영 주체 중 주민조직 직접 운영을 통한 주민들의 역량 강화 및 지역사회 발전과 공동체 의식을 공고히 할 수 있는 발판이 마련될 것이다.

최근 전 세계적으로 전례 없는 홍수와 극심한 폭염이 발생하면서 급속한 기후 변화의 심각성에 대한 세계적 인식이 높아졌다. 태양광 발전시설의 사회적 수용성과 안전성을 적극 홍보하는 한편, 국가 차원에서 정책 결정과 사업 운영을 최적화하기 위해 노력하고 있다. 본 연구는 영남·호남권 12개 주요 시·도의 태양광 발전설비 효율을 지역 에너지자원 지원 시스템과 기상자료를 활용한 DEA(Data Envelopment Analysis)를 활용하여 분석하였다. 첫째, 지역 내 지리적 범위의 차이는 발전효율의 성능적 평가의 차이점이 발생하는 것을 알 수 있었다. 둘째, 경제적 측면과 환경적 측면을 모두 고려한 태양광 발전시설에 대한 최적의 공간정보시스템의 중요성을 강조한다. 국내 신재생에너지 발전시설의 입지적 조건 개선으로 거시적 측면의 운영을 질적으로 보완하여 에너지 정책적 지원 필요성을 시사하며, 에너지 투자사업의 경제성 및 타당성을 제시하고자 한다.

The objective of this study is to investigate the safety awareness and effectiveness of the education and training for employees engaged in radiological emergency organization of the Korea Atomic Energy Research Institute (KAERI). In 2022, the questionnaire for the education satisfaction survey was revised to regulary evaluate the effect of edcation on perceptions of importance on emergency preparedness for nuclear research facilities. In line with, a standard questionnaire was created which covers 3 factors and 9 attributes, and the evaluation indicatior is based on a 5-point Likert scale. In 2023, the education on radiological emergency preparedness was conducted for 235 emergency staff. From May 24 to July 13, 2023, data was collected from a total of 235 emergency response personnels, including 28 new staffs and 207 maintenance staffs. Aa a result of response analysis, it was identified that education for radiological emergency response had a significant correlation with the promoting safety culture. It was found that senior emergency personnel with more years of experience are highly interested in radioactive disaster prevention and actively participate in and training. On the other hand, it was presented that new and less experienced groups tend to have a relatively high scored of the risk perception of nuclear research facilitites. Therefore, it is necessary to improve the practical curriculum in order to increase the participation of junior disaster prevention personnel in education and training, ensuring that they correctly recognize the risk of research facilities. This results are expected to be used to improve the quality of education and drills for radiological emergency response at KAERI.

One of the important components of a nuclear fuel cycle facility is a hot cell. Hot cells are engineered robust structures and barriers, which are used to handle radioactive materials and to keep workers, public, and the environment safe from radioactive materials. To provide a confinement function for these hot cells, it is necessary to maintain the soundness of the physical structure, but also to maintain the negative pressure inside the hot cell using the operation of the heating, ventilation, and air conditioning (HVAC) systems. The negative pressure inside the hot cells allows air to enter from outside hot cells and limits the leakage of any contaminant or radioactive material within the hot cell to the outside. Thus, the HVAC system is one of the major components for maintaining this negative pressure in the hot cell. However, as the facility ages, all the components of the hot cell HVAC system are also subject to age-related deterioration, which can cause an unexpected failure of some parts. The abnormal operating condition from the failure results in the increase of facility downtime and the decrease in operating efficiency. Although some major parts are considered and constructed in redundancy and diversity aspects, an unexpected failure and abnormal operating condition could result in reduction of public acceptance and reliability to the facility. With the advent of the 4th Industrial Revolution, prognostics and health management (PHM) technology is advancing at a rapid pace. Korea Hydro & Nuclear Power, Siemens, and other companies have already developed technologies to constantly monitor the integrity of power plants and are applying the technology in the form of digital twins for efficiency and safety of their facility operation. The main point of PHM, based on this study, is to monitor changes and variations of soundness and safety of the operation and equipment to analyze current conditions and to ultimately predict the precursors of unexpected failures in advance. Through PHM, it would be possible to establish a maintenance plan before the failure occurs and to perform predictive maintenance rather than corrective maintenance after failures of any component. Therefore, it is of importance to select appropriate diagnostic techniques to monitor and to diagnose the condition of major components using the constant examination and investigation of the PHM technology. In this study, diagnostic techniques are investigated for monitoring of HVAC and discussed for application of PHM into nuclear fuel cycle facilities with hot cells.

The Korea Atomic Energy Research Institute (KAERI) has facilities that are operated for the purpose of treating radioactive wastes and storing drums before sending them to a disposal site. Domestic regulations related to nuclear facility require radiological dose assessment resulting from release of gaseous radioactive effluent of nuclear facilities. In this study, ICRP-60-based dose conversion factors were applied to evaluate the radiation dose to residents in the event of operation and accident for the radioactive waste management facilities in KAERI. The radioactive gaseous effluent generated from each facility diffuse outside the exclusion area boundary (EAB), causing radiation exposure to residents. To evaluate the external exposure dose, the exposure pathways of cloudshine and radioactive contaminated soil were analyzed. The internal exposure dose was estimated by considering the exposure from respiration and ingestion of agricultural and livestock products. The maximum individual exposure dose was evaluated to be 1.71% compared to the dose limit. The assumed situation used for accidental scenarios are as follows; A fire inside the facility and falling of radioactive waste drum. It was a fire accident that caused the maximum exposure dose to individual and population living within an 80 km radius of the site. At the outer boundary of the low population zone (LPZ), the maximum effective dose and thyroid equivalent dose were estimated as 8.92 E-06% and 5.29 E-06%, respectively, compared to the dose limit. As a result of evaluating the radiological exposure dose from gaseous emissions, the radioactive waste treatment facilities and its supplementary facilities meet the regulations related to nuclear facility, and are operated safely in terms of radiological environmental impact assessment.

In the nuclear fuel cycle (NFC) facilities, the failure of Heating Ventilation and Air Conditioning (HVAC) system starts with minor component failures and can escalate to affecting the entire system, ultimately resulting in radiological consequences to workers. In the field of air-conditioning and refrigerating engineering, the fault detection and diagnosis (FDD) of HVAC systems have been studied since faults occurring in improper routine operations and poor preventive maintenance of HVAC systems result in excessive energy consumption. This paper aims to provide a systematic review of existing FDD methods for HVAC systems therefore explore its potential application in nuclear field. For this goal, typical faults and FDD methods are investigated. The commonly occurring faults of HVAC are identified through various literature including publications from International Energy Agency (IEA) and American Society of Heating, Refrigerating and Air-Conditioning Engineers (ASHRAE). However, most literature does not explicitly addresses anomalies related to pressure, even though in nuclear facilities, abnormal pressure condition need to be carefully managed, particularly for maintaining radiological contamination differently within each zone. To build simulation model for FDD, the whole-building energy system modeling is needed because HVAC systems are major contributors to the whole building’s energy and thermal comfort, keeping the desired environment for occupants and other purposes. The whole-building energy modeling can be grouped into three categories: physics-based modeling (i.e., white-box models), hybrid modeling (i.e., grey-box models), and data-driven modeling (i.e., black-box models). To create a white-box FDD model, specialized tools such as EnergyPlus for modeling can be used. The EnergyPlus is open source program developed by US-DOE, and features heat balance calculation, enabling the dynamic simulation in transient state by heat balance calculation. The physics based modeling has the advantage of explaining clear cause-and-effect relationships between inputs and outputs based on heat and mass transfer equations, while creating accurate models requires time and effort. Creating a black-box FDD model requires a sufficient quantity and diverse types of operational data for machine learning. Since operation data for HVAC systems in existing nuclear cycle facilities are not fully available, so efforts to establish a monitoring system enabling the collection, storage, and management of sensor data indicating the status of HVAC systems and buildings should be prioritized. Once operational data are available, well-known machine learning methods such as linear regression, support vector machines, random forests, artificial neural networks, and recurrent neural networks (RNNs) can be used to classify and diagnose failures. The challenge with black-box models is the lack of access to failure data from operating facilities. To address this, one can consider developing black-box models using reference failure data provided by IEA or ASHRAE. Given the unavailability of operation data from the operating NFC facilities, there is a need for a short to medium-term plan for the development of a physics-based FDD model. Additionally, the development of a monitoring system to gather useful operation data is essential, which could serve both as a means to validate the physics-based model and as a potential foundation for building data-driven model in the long term.

Kori unit 1 and Wolsong unit 1 were permanently shut down in 2017 and 2019, respectively. Both plants were decided to demolish the building without reuse. Large structures must be demolished after removing systems and components in the building, and in the case of large structures, thorough planning is required because of the large scale of work. Therefore, in this study, important considerations in the phase of the demolition plan of large structures when decommissioning were analyzed. The demolition of large structures at nuclear facilities is major one phase of work within a broader decommissioning plan. Furthermore, the actual demolition of the structure (i.e., physical process) represents the last step in a process that begins with extensive planning and analysis. The National Demolition Association (NDA) has provided checklist items that should be considered before the start of a commercial demolition project and/or in the bid process. Important Considerations in the Phase of the demolition plan of large structures when decommissioning of nuclear facilities are Site knowledge and programs, Engineering survey/demolition plan, Hazardous and radioactive materials, Open air demolition, Financial and project management, Permits, Code adherence, and Special programs, Disposal pathway, Final site condition. The results of this study can be used as a basis for the Planning large structures demolition of the Kori unit 1 and Wolsong unit 1.

For safe and successful decommissioning, it is one of the most important procedures that establishing the goal and complying with regulations of which final status of decommissioned site and building. The dose criteria for cyclotron facilities should be established and applied to reuse the site and building, since building and component of a cyclotron facility have been activated by incident secondary neutrons from radioactive isotope processes (e.g. 18O(p,n)18F, etc.). Furthermore, appropriate approaches should be applied to demonstrate compliance with the dose criteria for reliability of reuse. It is of noted that U.S. NRC (Nuclear Regulatory Commission) has confirmed that the residual radioactivity which distinguishable from background radiation results in a TEDE (Total Effective Dose Equivalent) does not exceed 25 mrem (0.25 mSv) per year as radiological criteria for unrestricted use of not only nuclear power plants but also cyclotron facilities referred to 10 CFR Part 20.1402. In addition, U.S. NRC noted the two approaches (i.e. dose assessment methods and, DCGL and final status surveys) which can be applied for demonstrating compliance with the dose criteria of 10 CFR Part 20 and recommended DCGL and FSS approach based on advantages and disadvantages of the two approaches. In order to using DCGL and FSS approach, U.S. NRC suggested screening approach; using DandD Version 2 which assesses TEDE under ICRP 28 and site-specific approach; using all models or computational codes which approved by NRC staff. There are several foreign cases that release of cyclotron facilities after decommissioning (i.e. U.S. and Japan). U.S., for examples, there are two DCGL approach cases and one dose modeling case based on 25 mrem per year same as reactor facilities. The dose modeling case, however, which may not be really used in Korea because of its low applicability. On the other hand, Japan case did not establish any radiological criteria for site and building reuse such as DCGL and just confirm “no more contamination” which is all residual radioactivity is lower than MDC based on real survey. Japan case also may not be used in Korea since criteria of “no more contamination” is not clear and hard to apply for all sites. Considering regulations and criteria for site release and reuse in Korea, this study aims to suggest radiological criteria and the demonstration approach of compliance for decommissioning of cyclotron facilities based on Nuclear Safety Acts and NSSC notices.

The type of radioactive waste that may occur in the process of nuclear power plant dismantling can be classified into solid, liquid, gas, and mixed waste. The amount of these wastes must be defined in the Final Decommissioning Plan for approval of the licensing. Also, in the case of Metal radioactive waste, it is necessary to calculate the generation amount in order to treat radioactive waste at a Radioactive Waste Treatment Facility (RWTF). Since a large quantity of metal radioactive waste is generated during the decommissioning of a nuclear power plant, the application of a metal melter for reduction is considered. The metal waste is heated to a temperature above the melting point and separated into liquid and gas forms. Nuclides existing on the surface of metal waste vaporize in a melting furnace to become dust or collect in sludge. Nonvolatile nuclides such as Co, Fe and Mn remain in ingot, but other nuclides can be captured and reduced with dust and sludge. And the types of melting furnaces to be applied can be broadly classified into Atmospheric Induction Melter (AIM) and Vacuum Induction Melter (VIM). Therefore, this review intends to compare the two types of metal furnaces to be included in RWTF.

A disposal of radioactive wastes is one of the urgent issues in worldwide. Considering upcoming plans for decommissioning of nuclear power plants, this problem is unavoidable and should be discussed very thoughtfully before long. There are variety of methods to deal with radioactive wastes, including Incineration process, conventional gasification process and plasma gasification process and so on. Among them, plasma gasification process is in the limelight due to its ecofriendly features and very large volume reduction effects. So, lots of countries like Japan, Taiwan, Russia, Bulgaria are already utilizing commercial plasma melting facilities and researching their own characteristics & disposal abilities and so on. Within the scope of this paper, I would like to introduce other countries current status of plasma melting facilities, and reach the conclusion on the directions to go for realistic radioactive wastes treatment.