• 제목/요약/키워드: ALARA evaluation

검색결과 13건 처리시간 0.022초

Preliminary ALARA residual radioactivity levels for Kori-1 decommissioning and analysis of results and effects of remediation area

  • Seo, Hyung-Woo;Yu, Ji-Hwan;Kim, Gi-Lim;Son, Jin-Won
    • Nuclear Engineering and Technology
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    • 제54권3호
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    • pp.1136-1144
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    • 2022
  • The effects of nearby residents and the public by the residual contamination from the decommissioning of nuclear facilities should comply with the dose criteria, and whether additional remediation action is necessary from the ALARA perspective must be determined. Therefore, we analyzed the requirements of ALARA action levels and performed preliminary ALARA evaluation. The ratio of residual contamination concentration to DCGL was calculated for the basement fill and the building occupancy mode. The results showed that the additional remediation actions below DCGL are not justified. In addition, we analyzed the effect of remediation area. It was noted that the increase of the remediation area showed a positive correlation with the Conc/DCGL value in the basement fill mode. On the other hand, in the building occupancy mode, since the floor area of the building is the target of remediation and has the effect of increasing the same as the evaluation area of the building occupants, but due to the difference in the amount of increase, the Conc/DCGL showed a negative correlation. We expect the approach and method of ALARA evaluation can be utilized for concrete cost-benefit calculation during the decommissioning or at the time of remediation.

External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 1

  • Byon, Jihyang;Park, Sangjune;Kim, Yangjin;Ahn, Seokyoung
    • Nuclear Engineering and Technology
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    • 제54권5호
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    • pp.1781-1788
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    • 2022
  • The containment building Kori Unit 1 may require sequential steps for full decommissioning. This study assumes that the containment building is to be used as an auxiliary building that handles nuclear power systems and materials during decommissioning before conversion into a greenfield. Through the derivation of guidelines and dose evaluation, it was confirmed whether the radiation workers were satisfied with the ALARA decision. The specific modeling of the external radiation exposure was performed based on the facility investigation procedures. The external radiation specific derived concentration guideline levels (DCGLs) for radiation workers in containment building were obtained using the RESRAD-BUILD code and were applied to the VISIPLAN 3D ALARA Planning Tool code to calculate the working dose and check worker safety. The derivation of site-specific and realistic DCGLs and dose evaluation via 3D modeling can contribute to the scenario development for the decommission and remediation of containment building.

소아 구내촬영 시 방사선량 평가 및 최적화 방안에 대한 연구 (A Study of Radiation Dose Evaluation and Optimization Methods for Intra Oral Dental X-ray in Pediatric Patient)

  • 이현용;조용인
    • 대한방사선기술학회지:방사선기술과학
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    • 제44권3호
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    • pp.195-203
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    • 2021
  • Although intra oral dental x-ray is a lower dose than other radiological examinations, pediatric patients are known to have a higher risk of radiation damage than adults. For this reason, pediatric dental x-ray requires management of dose evaluation and imaging conditions during the examination. In this study, the dose calculation program ALARA-Dental(child/adult) was used to evaluate the organ dose and effective dose exposed to each examination site during intra oral imaging of children during dental radiographic examination, and dose analysis according to the imaging conditions was performed. As a result, the highest organ dose distribution was shown at 0.044 ~ 0.097 mGy in all are as of the mucous membrane of oral cavity except for the maxillary incisors and canines. Also, in the case of the thyroid gland, the maxillary canine and maxillary premolar examination showed 0.027 and 0.020 mGy, respectively, and the dose distribution was 15.4% to 70.0% higher than that of the mandibular examination. As for the effective dose calculated during intra oral imaging, the maxillary anterior and canine examinations showed the highest effective doses of 0.005 and 0.004 mSv, respectively, and the maxillary area examination showed a higher dose distribution on average than the mandible.

전립선암의 방사선 치료 시 주변 정상장기 피폭선량을 이용한 암발생확률 평가 (Evaluation of Cancer Incidence Rate using Exposure Dose to Surrounding Normal Organs during Radiation Therapy for Prostate Cancer)

  • 이주아
    • 한국방사선학회논문지
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    • 제16권3호
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    • pp.351-356
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    • 2022
  • 전립선암의 방사선치료 시 사용되는 세기조절방사선치료와 부피적회전방사선치료시 발생하는 광중성자선량을 측정하여, 암 발생률을 평가하며 기초자료를 제공하고자 하였다. Rando phantom에 중성자 측정용 광자극발광선량계를 복부와 갑상선에 위치시킨 상태에서 발생하는 광중성자선량을 측정하였다. 연구결과 세기조절방사선치료(7 portal)가 부피적회전방사선치료보다 복부와 갑상선 위치에서 모두 높게 측정되었다. ICRP 103의 명목위험계수를 이용하여 암 발생확률을 평가하였을 때, 세기조절방사선치료시 대장과 갑상선의 피폭으로 인한 암발생확률은 1,000명 당 9.9명 이었으며, 부피적회전방사선치료시는 1,000명 당 3.5명이었다. ALARA(As low as reasonably archievable)원칙에 의거하여 방사선치료계획 수립에 있어서 정상장기들의 피폭선량의 최소화를 위한 가이드라인이 되리라 사료된다.

A study on characteristics and internal exposure evaluation of radioactive aerosols during pipe cutting in decommissioning of nuclear power plant

  • Kim, Sun Il;Lee, Hak Yun;Song, Jong Soon
    • Nuclear Engineering and Technology
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    • 제50권7호
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    • pp.1088-1098
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    • 2018
  • Kori unit #1, which is the first commercial nuclear power plant in Korea, was permanently shutdown in June 2017, and it is about to be decommissioned. Currently in Korea, researches on the decommissioning technology are actively conducted, but there are few researches on workers internal exposure to radioactive aerosol that is generated in the process of decommissioning nuclear power plants. As a result, the over-exposure of decommissioning workers is feared, and the optimal working time needs to be revised in consideration of radioactive aerosol. This study investigated the annual exposure limits of various countries, which can be used as an indicator in evaluating workers' internal exposure to radioactive aerosol during pipe cutting in the process of decommissioning nuclear power plants, and the growth and dynamics of aerosol. Also, to evaluate it, the authors compared/analyzed the cases of aerosol generated when activated pipes are cut in the process of nuclear power plants and the codes for evaluating internal exposure. The evaluation codes and analyzed data conform to ALARA, and they are believed to be used as an important indicator in deriving an optimal working time that does not excess the annual exposure limit.

Korea Total Diet Study-Based Risk Assessment on Contaminants Formed During Manufacture, Preparation and Storage of Food

  • Kwon, Kisung;Jo, Cheon-Ho;Choi, Jang-Duck
    • 한국식품위생안전성학회지
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    • 제36권3호
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    • pp.213-219
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    • 2021
  • 식품의 제조, 가공, 조리 및 저장 중 많은 유해물질이 발생하며 이들은 소량이지만 장기간 노출되면 식품안전에 위협이 될 수 있다. 본 연구에서는 식품의약품안전처에서 수행한 총 식이조사(TDS) 자료를 기반으로 우리나라에서 식품섭취를 통한 이들 주요 유해물질에 대한 노출 및 위해평가 상황을 파악하고 소비자 및 기업으로 하여금 관련 위험을 저감하는 방안을 제시하고자 하는 것이다. 식품의 제조, 가공, 조리 및 저장 중 생성 유해물질 중 대표적인 아크릴아미드, 퓨란, 에틸 카바메이트, 3-MCPD, 바이오제닉 아민류, 니트로아민류 화합물, 다환 방향족화합물, 벤젠 등에 대한 식이를 통한 노출량을 조사하고 위해평가를 수행한 바, 아크릴아미드 및 퓨란의 경우 노출안전역(MOE) 10,000이하로 저감화 우선 물질로 판단되며, 나머지 물질 등의 경우 모두 노출안전역이 10,000 또는 100,000 이상으로 안전한 수준에 있는 것으로 나타났음. 그러나 향후 지속적으로 모니터링을 수행하고 ALARA 원칙에 따라 가능한 노출 저감화를 위해 노력을 기울여야한다.

철도 안전 설비의 정량적 위험평가 기술 (Technical Review on the QRA of Railway Safety Facilities)

  • 최권희;김유호;이종우;송중호;송광열
    • 대한안전경영과학회지
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    • 제13권3호
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    • pp.1-8
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    • 2011
  • The overall goal of a safety based railroad system is either to eliminate hazards in designing or to minimize the possibility of it. In order to indicate system safety or low risk although it may not be possible to achieve zero risk conditions, first, it shall ensure that any disasters would occur due to system operation because the prescribed specifications are properly fulfilled and there are no failures of any kind. Second, the risk of faults or failures leading to a mishap must be eliminated or minimized by using fault-tolerance or fail-safe procedures. This paper will attempt to summarize the personal and social risk criterion at widely scattered points, presently used as a safety approach in all over EU, in order to establish the step by step procedures of the detailed standard for railway facilities. In addition, we present the new safety analysis method using the SIL-based evaluation standard and the Reachability Graph of the Petri Net.

Establishment of the Korean Tolerable Daily Intake of Bisphenol A Based on Risk Assessments by an Expert Committee

  • Choi, Chan-Woong;Jeong, Ji-Yoon;Hwang, Myung-Sil;Jung, Ki-Kyung;Lee, Kwang-Ho;Lee, Hyo-Min
    • Toxicological Research
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    • 제26권4호
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    • pp.285-291
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    • 2010
  • Recently, reproductive and neurobehavioral effects of bisphenol A (BPA) have been documented, and thus a review was requested for BPA management direction by the government. Therefore, this study was performed to establish a Korean tolerable daily intake (TDI) for BPA. An expert committee, consisting of specialists in fields such as toxicology, medicine, pharmacology, and statistics, was asked to evaluate BPA health based guidance values (HbGVs). Although many toxicological studies were reviewed to select a point of departure (POD) for TDI, rat and mouse reproductive studies by Tyl et al. (2002, 2006), which were performed according to GLP standards and OECD guidelines, were selected. This POD was the lowest value determined from the most sensitive toxicological test. The POD, a NOAEL of 5 mg/kg bw/day, was selected based on its systemic toxicity as critical effects. An uncertainty factor of 100 including interspecies and intraspecies differences was applied to calculate the TDI. According to the evaluation results, a TDI of BPA for Korean was suggested at 0.05 mg/kg bw/day. In addition, the BPA exposure level based on food consumption by the Korean population was estimated as 1.509 ${\mu}g/kg$ bw/day, and the HI was evaluated at 0.03 when the TDI of 0.05 mg/kg bw/day was applied. This HI value of 0.03 indicated that hazardous effects would not be expected from BPA oral exposures. Although highly uncertain, further studies on low dose neurobehavioral effects of BPA should be performed. In addition, it is recommended that the 'as low as reasonably achievable' (ALARA) principle be applied for BPA exposure from food packaging materials in newborn infants and children.

양성자 치료 시 방사선 작업 종사자에게 미치는 방사선 피폭에 대한 평가 (Evaluation on the Radiation Exposure of Radiation Workers in Proton Therapy)

  • 이승현;장요종;김태윤;정도형;최계숙
    • 대한방사선치료학회지
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    • 제24권2호
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    • pp.107-114
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    • 2012
  • 목 적: 기존의 광자선을 이용한 선형가속기와는 달리, 양성자 치료의 경우 물질과의 상호작용으로 발생되는 중성자를 비롯한 여러 핵종 등으로 인해 다량의 이차방사선이 생성되기 때문에 방사선 작업 종사자의 피폭은 더욱 주의 깊은 관심이 필요하다. 이에 방사선 측정 시에 널리 이용되고 있는 열형광선량계를 이용하여 방사선 작업 종사자의 피폭정도를 평가하고 이를 토대로 양성자 치료 시 방사선 피폭선량에 관한 기초 자료를 제시하고자 한다. 대상 및 방법: 본원의 양성자 치료실에서 근무한 방사선 작업 종사자를 대상으로 열형광선량계 뱃지를 이용해 피폭현황을 측정한 데이터를 비교했다. 양성자의 빔 라인 주변에서 발생하는 이차방사선의 신체부위별 피폭선량 분포를 알아보고자 신체부위(외안각, 목, 유두점, 배꼽, 등, 손목)에 가로, 세로가 각각 3 mm인 정사각형 모양의 열형광선량계를 부착하여 일일 8시간의 근무시간동안 유지하도록 하였고 총 80시간 측정하여 평균 데이터를 얻었다. 그리고 치료실 내 공간적인 방사선량의 분포를 보기 위하여 빔 사출구, PPS (Patient Positioning System), Pendant, 차폐체보관장, DIPS (Digital Image Positioning System) Console, 출입통로에 각각 열형광선랑계를 부착하고 일일 근무시간 동안의 평균 방사선량을 측정하였다. 결 과: 방사선 작업 종사자의 열형광선량계 뱃지로 측정된 피폭량을 조사한 결과 분기별 평균 0.174 mSv, 연평균 0.543 mSv로 나타났고 신체부위별로 측정한 결과에서 가장 많은 피폭량을 보인 곳은 목이였으며 가장 적은 피폭량을 보인 곳은 등(양견갑골 상각을 이은 선의 중간 지점)으로 나타났다. 작업 동선에 따른 공간적 방사선량을 알아본 결과에서는 빔 사출구 근처에서 상대적으로 높게 나타났고 거리가 멀어짐에 따라 줄어들었다. 결 론: 적은 양의 피폭일지라도 동일 장소에서 장기 근무하게 되면 피폭 누적량은 증가할 수밖에 없고 특정 부위의 누적량은 건강상의 위험을 가져다 줄 수도 있다. 그러므로 국제 방사선 방어 위원회가 권고하는 ALARA의 원칙에 따라 가능한 합리적으로 감소시킬 수 있도록 스스로 개인별 피폭관리에 철저를 기하고 피폭을 최소화시키는데 최선의 노력을 다해야 할 것이다.

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심장동맥 조영 검사 시 검사 조건에 따른 환자 선량 평가 (Evaluation of Radiation Dose to Patients according to the Examination Conditions in Coronary Angiography)

  • 조용인
    • 대한방사선기술학회지:방사선기술과학
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    • 제46권6호
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    • pp.509-517
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    • 2023
  • This study analyzed imaging conditions and exposure index through clinical information collection and dose calculation programs in coronary angiography examinations. Through this, we aim to analyze the effective dose according to examination conditions and provide basic data for dose optimization. In this study, ALARA(As Low As Reasonably Achievable)-F(Fluoroscopy), a program for evaluating the radiation dose of patients and the collected clinical data, was used. First, analysis of imaging conditions and exposure index was performed based on the data of the dose report generated after coronary angiography. Second, after evaluating organ dose according to 9 imaging directions during coronary angiography, with the LAO fixed at 30°, dose evaluation was performed according to tube voltage, tube current, number of frames, focus-skin distance, and field size. Third, the effective dose for each organ was calculated according to the tissue weighting factors presented in ICRP(International Commission on Radiological Protection) recommendations. As a result, the average sum of air kerma during coronary angiography was evaluated as 234.0±112.1 mGy, the dose-area product was 25.9±13.0 Gy·cm2, and the total fluoroscopy time was 2.5±2.0 min. Also, the organ dose tended to increase as the tube voltage, milliampere-second, number of frames, and irradiation range increased, whereas the organ dose decreased as the FSD increased. Therefore, medical radiation exposure to patients can be reduced by selecting the optimal tube voltage and field size during coronary angiography, maximizing the focal-skin distance, using the lowest tube current possible, and reducing the number of frames.