• 핵의학기술
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• 제13권3호
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• pp.110-122
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• 2009

목적: 최근 의료기관평가제도는 의료의 질에 대한 병원들의 관심을 높게 하고 그것을 향상시키기 위한 활동을 활발히 전개하고 있다. 또한 추가된 항목인 환자의 위험관리에 대해서도 많은 관심을 보이고 있다. 의정부성모병원 핵의학과는 2008년도 PET/CT도입으로 시작된 부서내 리모델링은 과내 구조 및 업무 프로세스에 많은 변화를 가져왔다. 따라서 변경된 구조와 기존의 업무 처리방식은 미처 알지 못하는 위험요인을 내포하게 되었다. 그러므로 영상 검사 과정에서 발생할 수 있는 위험요인을 다각도로 찾고 분석하여, 부서의 특수한 환경에 맞는 위험관리 프로세스와 위험요인 제거업무를 포함한 개선 활동을 목적으로 한다. 실험재료 및 방법: 핵의학과의 새로워진 프로세스를 다각도로 분석하여 첫째, 위험관리 응대메뉴얼을 제작하여 교육후 실제 업무에 적용한다. 결과분석은 전년도 위험사고 발생건수와 개선활동 후 위험사고 발생건수를 비교하였다. 둘째, 위험관리 홍보동영상은 제작 후 검사전 해당 환자에게 상영하였고 그 후 자체 제작된 설문지로 해당 환자 100명에게 만족도 조사를 하였다. 셋째, 위험요소를 개선할 수 있는 시설물 참여형 개선활동을 통해서 위험요소를 제거하였다. 결과: 안전사고 발생건수는 개선활동이후 PET/CT와 감마카메라 영상 검사 모두 검사건수대비 투약오류, 낙상, 충돌 등의 안전사고가 0건으로 조사되었다. 설문조사 결과는 동영상 상영 후 검사진행과정 이해 74%, 불안감해소 81%로 "만족한다"는 결과가 조사되었다. "위험요소에 대해 주의했습니까?" 라는 물음의 경우 PET/CT는 94%, 감마카메라는 89%가 주의했다는 결과로 조사되었다. 개선활동을 통해서 핵의학과내에서의 고객위험관리를 효과적으로 수행할 수 있었다. 결론: 본 개선활동을 통하여 영상 검사 시 산재된 위험요소를 체계적으로 나열하고 분석하는 계기가 되었다. 또한 안전사고에 대처하는 방사선사의 업무방법에서도 기준이 되는 응대메뉴얼을 적용시킨다면 안전사고의 최소화와 안전사고시 체계적인 피드백이 가능함을 알 수 있었다. 위험요소를 알려주는 방법론적인 부분에서도 일상생활에서 쉽게 접할 수 있는 시청각자료로 제공 되었을 때 보다 효과적이였다. 따라서 이런 활동이 지속적이고 세부화 된 업그레이드 작업을 통해서 환자들에게 제작되어 제공된다면 핵의학 검사 이용의 안전성과 편리성에 도움을 줄 수 있으리라 생각된다.

• Nuclear Engineering and Technology
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• 제39권4호
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• pp.237-248
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• 2007

Sodium-cooled fast reactor is considered in France as a potential candidate for a prototype of 4th generation system to be built by 2020. A detailed working program has been launched recently to identify by 2012 the potential improvement tracks for later industrial development of these reactors. The goals for innovation are first identified: Progress of the safety with a special attention to severe accidents risk minimization and mitigation (defense in depth approach); Economic competitiveness of the system mainly by reducing the capital cost, the investment risks by enhancing in service inspection and repair capacities, and raising the availability; Sustainability with fissile material management while reducing the proliferation risk; capacity for long-lived waste transmutation.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.733-743
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• 2016

The purpose of this study is to present a rational depreciation method for a pyroprocess cost calculation. Toward this end, the so-called advanced decelerated depreciation method (ADDM) was developed that complements the limitations of the existing depreciation methods such as the straight-line method and fixed percentage of declining-balance method. ADDM was used to show the trend of the direct material cost and direct labor cost compared to the straight-line or fixed percentage of the declining-balance methods that are often used today. As a result, it was demonstrated that the depreciation cost of the ADDM, which assumed a pyroprocess facility's life period to be 40 years with a deceleration rate of 5%, takes up 4.14% and 27.74% of the pyroprocess unit cost ($781/kg heavy metal) in the $1^{st}$ and final years, respectively. In other words, it was found that the ADDM can cost the pyroprocess facility's capital investment rationally every year. Finally, ADDM's validity was verified by confirming that the sum of the depreciation cost by year, and the sum of the purchasing cost of the building and equipment, are the same.

• Nuclear Engineering and Technology
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• 제56권7호
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• pp.2875-2880
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• 2024

The development of nuclear power plants is in three phases. The first phase is a consideration before the decision on the NPP construction program is approved, the second phase is the preparatory work for making contracts and preparing for the construction of NPP after the NPP construction policy is approved, and the third phase is contracting, licensing and building the first NPP. As a volcanically active country, Indonesia contains over 130 active volcanoes that are part of the Pacific Ring of Fire. The volcanic aspect is one of the safety factors considered while deciding the location of an NPP. Research on the potential of natural external risks to the determination of nuclear power plants in Indonesia, including the volcanic aspect, has been conducted based on the safety reference or safety guide of the IAEA and the Nuclear Energy Regulatory Body (BAPETEN) Regulation. Due to technological advancements, safety needs have evolved so the existing Indonesia National Standard (SNI) must be updated to comply with BAPETEN regulations. The substance in SNI 18-2034-1990 relating to volcanic features seems less relevant in actual conditions, given that more complete and exact criteria for determining a site guarantee the safety and health of residents and surrounding the environment site. The study intends to conduct a gap analysis of volcanic issues in SNI and volcanic regulations. The method used is identification requirements for volcanic aspects in SNI 18-2034-1990 about Determining Site of Nuclear Reactor Guidance with BAPETEN Chairman Regulation (BCR) number 4 of 2018 about Nuclear Installation Site Evaluation Safety Provisions and BCR number 5 of 2015 about Evaluation of Nuclear Installation Sites for Volcanic Aspects, and analysis uses a qualitative method of inductive techniques. The outcome of this research applies to suggesting a revision of SNI number 18-2034-1990, especially the volcanic aspect.

• 융합보안논문지
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• 제17권3호
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• pp.73-81
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• 2017

2009년 4월 미국 오바마 대통령의 프라하 연설을 계기로 국제사회는 핵안보 증진과 핵테러리즘 저지를 위해 2010년부터 2016년까지 4차례의 핵안보정상회의를 개최하였다. 핵안보정상회의는 테러리스트들이 핵무기 또는 핵 분열성 물질의 획득 노력을 저지하기 위한 중대한 진전을 이루었으나 여전히 한계와 문제점을 남겼다. 이를 해결하기 위한 향후 국제 사회의 과제는 첫째, 양자간 협력과 다자간 핵안보 레짐 강화를 위한 공동의 노력을 재개하고, 참가국은 자국의 핵물질 방호와 핵시설 보안을 위한 공약 이행을 위해 노력해야한다. 둘째, 4차 핵안보정상회의에서 채택된 5개 행동계획에 따라 유엔, 국제원자력기구, 국제형사경찰기구(인터폴), 세계핵테러방지구상, 글로벌파트너십은 지속적인 핵안보 증진을 위해 임무를 수행해야한다. 셋째, 참가국들은 핵안보정상회의에서 다루지 못했던 군수용 핵물질의 관리와 방호에 대한 논의를 시작해야한다. 넷째, 핵안보의 국제법적 기반인 개정 핵물질방호협약과 핵테러억제협약의 이행을 강화하고, 핵시설에 대한 사이버 공격 대비 및 핵물질의 도난 불법거래 사보타주 저지를 위해 노력해야한다.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2018년도 춘계 학술논문 발표대회
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• pp.294-295
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• 2018

Nowadays, the construction industry utilizes 3D models in the designing process, on which research is being conducted to establish an automated system for project cost estimation in connection with information related to construction such as material unit costs and wages, beyond the level of design interference review and construction quantity estimation. In this process, the project cost is estimated in connection with unit price data after takeoff the quantity based on the 3D model attributes and data types. A way to reduce cost and risk would be first developing prototypes of some of essential buildings and works, comparing and validating the outcomes, and then extending to the whole scope, because estimates differ on the basis of the scope and level of 3D design models as well as the data accuracy. This study analyzes case studies of project cost estimation by computing the quantity on the basis of 3D model in the construction industry and explores methodologies and management measures applicable for estimating nuclear power plant construction project costs.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1210-1217
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• 2021

The analysis of ⁴¹Ca in concrete generated from the nuclear facilities decommissioning is critical for ensuring the safe management of radioactive waste. An analytical method for the determination of ⁴¹Ca in concrete is described. ⁴¹Ca is a neutron-activated long radionuclide, and hence, for accurate analysis, it is necessary to completely extract Ca from the concrete sample where it exists as the predominant element. The decomposition methods employed were the acid leaching, microwave digestion, and alkali fusion. A comparison of the results indicated that the alkali fusion is the most suitable way for the separation of Ca from the concrete sample. Several processes of hydroxide and carbonate precipitation were employed to separate ⁴¹Ca from interferences. The method relies on the differences in the solubility of the generated products. The behavior of Ca and the interfering elements such as Fe, Ni, Co, Eu, Ba, and Sr is examined at each separation step. The purified ⁴¹Ca was measured by a liquid scintillation counter, and the quench curve and counting efficiency were determined by using a certified reference material of known ⁴¹Ca activity. The recoveries in this study ranged from 56 to 68%, and the minimum detectable activity was 50 mBq g^-1 with 0.5 g of concrete sample.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2230-2243
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• 2022

The tin tailing processing industry in Malaysia has operated with minimal regard and awareness for material management and working environment safety, impacting the environment and workers in aspects of radiation and heavy metal exposure. RIA was conducted where environmental samples were analyzed, revealing concentrations of ²²⁶Ra, ²³²Th and ⁴⁰K between the range of 0.1-10.0, 0.0-25.7, and 0.1-5.8 Bq/g respectively, resulting in the AED exceeding UNCEAR recommended value and regulation limit enforced by AELB (1 mSv/y). Ra_eq calculated indicates that samples collected pose a significant threat to human health from gamma-ray exposure. Assessment of heavy metal content via pollution indices of soil and sediment showed significant contamination and enrichment from processing activities conducted. As and Fe were two of the highest metals exposed both via soil ingestion with an average of 4.6 × 10^-3 mg/kg-day and 1.4 × 10^-4 mg/kg-day, and dermal contact with an average of 5.6 × 10^-4 mg/kg-day and 6.0 × 10^-4. mg/kg-day respectively. Exposure via accidental ingestion of soil and sediment could potentially cause adverse non-carcinogenic and carcinogenic health effect towards workers in the industry. Correlation analysis indicates the presence of a relationship between the concentration of NORM and trace elements.

• Nuclear Engineering and Technology
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• 제47권3호
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• pp.293-305
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• 2015

In this paper, we suggest the conceptual design of a water-cooled reactor system for a low-pressure inherent heat sink nuclear desalination plant (LIND) that applies the safety-related design concepts of high temperature gas-cooled reactors to a water-cooled reactor for inherent and passive safety features. Through a scoping analysis, we found that the current LIND design satisfied several essential thermal-hydraulic and neutronic design requirements. In a thermal-hydraulic analysis using an analytical method based on the Wooton-Epstein correlation, we checked the possibility of safely removing decay heat through the steel containment even if all the active safety systems failed. In a neutronic analysis using the Monte Carlo N-particle transport code, we estimated a cycle length of approximately 6 years under 200 $MW_{th}$ and 4.5% enrichment. The very long cycle length and simple safety features minimize the burdens from the operation, maintenance, and spent-fuel management, with a positive impact on the economic feasibility. Finally, because a nuclear reactor should not be directly coupled to a desalination system to prevent the leakage of radioactive material into the desalinated water, three types of intermediate systems were studied: a steam producing system, a hot water system, and an organic Rankine cycle system.

• Membrane and Water Treatment
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• 제13권5호
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• pp.227-233
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• 2022

The objective of the study, to develop adsorbent based purifier for removal of radiological and nuclear contaminants from contaminated water. In this regard, 3-aminopropyl silica functionalized with ethylenediamine tetraacetic acid (APS-EDTA) adsorbent prepared and characterized by Fourier Transform Infrared Spectroscopy (FT-IR), Scanning Electron Microscopy (SEM) and X-ray Diffraction (XRD). Prepared APS-EDTA used for adsorptive studies of Cs(I), Co(II), Sr(II), Ni(II) and Cd(II) from contaminated water. The effect on adsorption of various parameters viz. contact time, initial concentration of metal ions and pH were also analyzed. The batch method has been employed using metal ions in solution from 1000-10000 ㎍/L, contact time 5-60 min., pH 4-10 and material quantities 50-200 mg at room temperature. The obtained adsorption data were used for drawing Freundlich and Langmuir isotherms model and both models were found suitable for explaining the metal ions adsorption on APS-EDTA. The adsorption data were followed pseudo second order reaction kinetics. The maximum adsorption capacity obtained 1.3037-1.4974 mg/g for above said metal ions. The results show that APS-EDTA have great potential to remove Cd(II), Co(II), Cs(I), Ni(II) and Sr(II) from aqueous solutions through chemisorption and physio-sorption.