• 한국환경보건학회지
• /
• 제38권4호
• /
• pp.332-339
• /
• 2012

Objectives: The purpose of this study was to prevent health problems and environmental contamination resulting from inappropriate management of dental wastes and to provide reference data for revision and supplementation of dental clinic waste management guidelines. Methods: From 640 total of dental clinics registered in 16 cities and counties in Gyeongsangnam-do, 100 (60 in Changwon (Masan, Changwon), 29 in Gimhae, and 11 in Jinju) were included in this study. From July 2010 to September 2010, investigators visited the 100 dental clinics and conducted survey interviews using a structured survey questionnaire regarding disposal methods for liquid wastes (suction pump, spittoon container waste, used liquid disinfectants, and X-ray developer), and disposal methods for solid waste (suction pump, spittoon container waste, and general medical waste). Results: All the 100 dental clinics were found to treat liquid waste from suction pumps and spittoon containers in the same manner as general waste water. Nineteen percent of the clinics treated solid waste that was not filtered through the filter of a suction pump as general waste. Fifty or more percent of the clinics treated solid waste in spittoon containers as general waste. Seventy percent of the clinics used disinfectant solution, although most of them treated used disinfectants in the same manner as general waste water. Some clinics treated used X-ray developer and X-ray fixer in the same manner as general waste water. In most of the clinics, used drapes were washed within the clinic. Conclusions: It was found that waste water and dental wastes at some dental clinics were treated in inappropriately. Thus, in conclusion, the development of guidelines regarding proper management of liquid and solid dental waste at dental clinics is required, and hygiene and environmental training for workers at dental clinics is necessary.

• 한국의학물리학회지:의학물리
• /
• 제25권1호
• /
• pp.8-14
• /
• 2014

의료분야에서 방사선 진료기술의 발전에 따라 방사성폐기물의 수량은 급속히 증가하고 있다. 방사성폐기물에는 주로 PET/CT에 사용하는 $^{18}F$을 비롯하여 핵의학검사에 사용하는 $^{99m}Tc$ 등과 같이 반감기가 매우 짧은 방사성동위원소가 함유되어 있다. 이를 처분하기 위하여 국제원자력기구(IAEA)는 개인선량($10{\mu}Sv/y$) 및 집단선량(1 man-Sv/y)과 핵종별 농도에 근거하여 각각 폐기물의 규제해제기준을 제시(IAEA Safety Series No 111-P-1.1, 1992 및 IAEA RS-G-1.7, 2004)하였다. 이 연구에서는 IAEA 기준에 따른 방사능농도를 측정하기 위하여, $^{18}F$, $^{99m}Tc$, $^{123}I$, $^{125}I$ 및 $^{201}TI$ 관련 방사성폐기물을 수집하고 측정용기를 준비하였다. 그리고 MCA를 이용한 감마방사능 측정, 감마계수기를 이용한 감마방사능 측정, 베타입자 방출 핵종의 방사능 측정방법 및 절차를 수립하고, 표준물질을 제작하여 교정하였다. 측정결과를 근거로 방사능 감쇠 유도식을 산출하였으며, 이를 이론식과 대비하여 고찰하였다. 이 연구 결과는 ISO 표준으로 추진할 예정이다.

• 핵의학기술
• /
• 제12권1호
• /
• pp.119-122
• /
• 2008

Radioiodine (I-131) Therapy has been known one of the methods treated with hyperthyroidism and thyroid tumor, using a separate ward. This technique has been already used for several decades, and its clinical efficacy proven. Today, Radioiodine takes a form of capsule through continuous development, so, 30 odd domestic hospitals run about 63 separate wards. And, its demands would increase continuously; because of tending upwards the patients had thyroid cancer. However, various kinds of wastes originate from a procedure of radioiodine therapy. Especially, when their radioactivity exceed permissible level (4 Bq/$cm^2$) set by Nuclear laws of the Republic of Korea, it regards as radioactive wastes, then, managed separately from origination to the last disposal.

• 한국환경과학회:학술대회논문집
• /
• 한국환경과학회 1996년도 가을 학술발표회 초록집
• /
• pp.66-66
• /
• 1996

• 대한위생학회:학술대회논문집
• /
• 대한위생학회 2004년도 심포지움
• /
• pp.28-44
• /
• 2004

• 한국생명과학회:학술대회논문집
• /
• 한국생명과학회 2005년도 국제학술심포지움 The 44th Annual Meeting of Korean Society for Life Science
• /
• pp.236-236
• /
• 2005

• 한국생명과학회:학술대회논문집
• /
• 한국생명과학회 2005년도 국제학술심포지움 The 44th Annual Meeting of Korean Society for Life Science
• /
• pp.101-101
• /
• 2005

• Nuclear Engineering and Technology
• /
• 제54권2호
• /
• pp.507-513
• /
• 2022

When X-ray energy above 8 MV is used, photoneutrons are generated by the photonuclear reaction, which activates the components of linear accelerator (linac). Safely managing the radioactive material, when disposing linac or replacing components, is difficult, as the standards for the radioactive material management are not clear in Korea. We surveyed the management status of radioactive components occurred from medical linacs in Korea. And we also measured the activation of each part of the discarded Elekta linac using a survey meter and portable High Purity Germanium (HPGe) detector. We found that most medical institutions did not perform radiation measurements when disposing of radioactive components. The radioactive material was either stored within the institution or collected by the manufacturer. The surface dose rate measurements showed that the parts with high surface dose rates were target, primary collimator, and multileaf collimator (MLC). ⁶⁰Co nuclide was detected in most parts, whereas for the target, ⁶⁰Co and ¹⁸⁴Re nuclides were detected. Results suggest that most institutions in Korea did not have the regulations for disposing radioactive waste from linac or the management procedures and standards were unclear. Further studies are underway to evaluate short-lived radionuclides and to lay the foundation for radioactive waste management from medical linacs.

• Nuclear Engineering and Technology
• /
• 제54권4호
• /
• pp.1456-1463
• /
• 2022

The aim of this work is to study the radiation shielding properties of cement samples with waste glass incortated into its composition. The mass attenuation coefficient (MAC) of the samples were experimentally determined to evaluate their radiation shielding ability. The experimental coefficient was evaluated using NaI detector for gamma energies between 59.53 keV and 1408.01 keV using different radioactive point sources Am-241, Eu-152, Co-60, and Cs-137, and the gamma transmission parameters half-value layer, mean free path, and transmission factor were calculated. The theoretical coefficient of the composites was determined using Geant4 and XCOM software. The results were also compared against Geant4 and XCOM simulations by calculating the relative deviation between the values to determine the accuracy of the results. In addition the mechanical properties (including Compressive and porosity) as well as the thermogravimetric analysis were tested for the present samples. Overall, it was concluded that the cement sample with 50% waste glass has the greatest shielding potential for radiation shielding applications and is a useful way to reuse waste glass.

• 공업화학
• /
• 제33권4호
• /
• pp.352-366
• /
• 2022

Nuclear power plant operations for electricity generation, rare-earth mining, nuclear medical research, and nuclear weapons reprocessing considerably increase radioactive waste, necessitating massive efforts to eradicate radioactive waste from aquatic environments. Cobalt (⁵⁸Co) and strontium (⁹⁰Sr) radioactive elements have been extensively employed in energy generation, nuclear weapon testing, and the manufacture of healthcare products. The erroneous discharge of these elements as pollutants into the aquatic system, radiation emissions, and long-term disposal is extremely detrimental to humans and aquatic biota. Numerous methods for treating radioactive waste-contaminated water have emerged, among which the adsorption process has been promoted for its efficacy in eliminating radioactive waste from aquatic habitats. The current review discusses the adsorptive removal of radioactive waste from aqueous solutions using low-cost adsorbents, such as graphene oxide, metal-organic frameworks, and inorganic metal oxides, as well as their composites. The chemical modification of adsorbents to increase their removal efficiency is also discussed. Finally, the current state of ⁵⁸Co and ⁹⁰Sr removal performances is summarized and the efficiencies of various adsorbents are compared.