• 제목/요약/키워드: radiological dose assessment

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유방암 근접치료 시 나노입자의 밀도에 따른 흡수선량 평가 (Evaluation of Absorbed Dose According to Nanoparticle Density During the Breast Cancer Brachytherapy)

  • 이득희;남지희;김정훈
    • 대한방사선기술학회지:방사선기술과학
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    • 제42권2호
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    • pp.131-135
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    • 2019
  • The purpose of this study was to evaluate the efficacy of brachytherapy of breast cancer by dose assessment which a steady increased in Korea women. The dose assessment was performed using the MCNPX program, a MonteCarlo simulation technique. The sources used for brachytherapy was 192Ir. And nanoparticle which used for dose enhancement was gold. The density of nanoparticle was 7, 18 and 30 mg. Evaluation of absorbed dose according to distance is measured at a distance of 30, 50, 100 and 200 cm from the patient. As a result, The breast absorbed dose results increased in proportion to the density of nanoparticle. And the surrounding organs were not significantly different according to the density. But, in some organs, the absorbed dose decreased as the density of nanoparticles increased. Absorbed dose according to the distance was in inverse proportion to distance.

유리선량계를 이용한 저선량 방사선의 마우스 피폭선량 연구 (A Study on Mice Exposure Dose for Low-dose Gamma-irradiation Using Glass Dosimeter)

  • 노성진;김효진;김현;정동혁;손태건;김정기;양광모;남상희;강영록
    • Journal of Radiation Protection and Research
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    • 제40권4호
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    • pp.202-210
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    • 2015
  • 저선량 조사는 낮은 선량을 지속적으로 장기간 조사시키기 때문에 조사되는 마우스들에 대한 선량분포를 정확히 알고 있어야만 한다. 본 연구는 저선량 방사선에 대한 생물학적 영향평가를 위하여 동남권원자력의학원 연구센터에 설치된 $^{137}Cs$ 조사장치에 대하여 마우스조사 실험 시 마우스에 원하고자 하는 선량을 전달하기 위한 방법에 대하여 연구를 수행하였다. 마우스에 원하고자 하는 정확한 선량을 전달하기 위하여 선원에 대하여 동일한 위치에 마우스 케이지 45개를 설치할 수 있는 아파트를 자체 개발하였으며, 개발된 마우스 아파트 시스템에 대한 선량평가를 하기 위하여 유리선량계(glass dosimeter)를 실험용 마우스 머리와 배에 삽입한 후 기존 조사 시스템과 자체 개발한 마우스 아파트 시스템에 대해 비교 선량평가를 수행하였다. 기존시스템의 조사방식에서 최대 42%의 선량차이를 보였으며 개발한 마우스 아파트 시스템은 6% 이내의 선량차이를 보였다. 본 연구를 통해 개발된 마우스 아파트를 활용한 저선량 방사선에 대한 생물학적 영향평가 연구는 전달하고자 하는 선량을 보다 정확하게 제공할 수 있으며, 생물학적 분석결과에 신뢰성을 확보할 수 있다.

진단용 방사성동위원소 취급 시 L-block 차폐기구 사용에 따른 핵의학 종사자의 장기 선량평가 (Organ Dose Assessment of Nuclear Medicine Practitioners Using L-Block Shielding Device for Handling Diagnostic Radioisotopes)

  • 강세식;조용인;김정훈
    • 대한방사선기술학회지:방사선기술과학
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    • 제40권1호
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    • pp.49-55
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    • 2017
  • 의료기관 내 핵의학 종사자는 방사성동위원소 취급 시 사용하는 선원의 종류, 방사능량, 차폐기구의 사용 여부에 따라 종사자 개인별로 광범위한 피폭선량을 나타낼 수 있다. 이에 본 연구에서는 몬테카를로 기법을 기반으로 한 모의실험을 통해 진단용 방사선원 취급 시 종사자의 장기별 선량평가와 L-block 차폐기구 사용에 따른 선량감소효과를 분석하였다. 그 결과, 방사선원의 취급 위치에 근접할수록 높은 장기선량 분포를 나타내었고, ICRP 조직가중치에 따라 유효선량 분포가 상이한 양상을 보였다. 또한 L-block 두께에 따른 선량감소효과는 차폐두께 증가에 따라 지수함수 분포로 감소되는 경향을 나타내었으며, 방사선원별 선량감소효과는 방출하는 감마선 에너지에 비례하여 낮은 차폐효과를 보였다.

유방촬영 시 몬테칼로 전사모사를 이용한 유방 성형 환자의 장기선량 평가 (Assessment of Organ Dose in Mammoplasty Patient by Monte Carlo Simulation during Mammography)

  • 김지수;조용인;김정훈
    • 대한방사선기술학회지:방사선기술과학
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    • 제43권5호
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    • pp.337-341
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    • 2020
  • Although the screening with a mammography has been shown to be economical, simple and effective in detecting breast cancer, it is accompanied by the risk from radiation. Therefore, this study analyzed the glandular dose and organ dose according to the target-filter combination and the presence and absence of implants using Monte Carlo simulation. The results indicate that at a tube voltage of 30 kV and a tube current of 50 mAs, the dose increased in the order of Mo/Mo. Mo/Rh, Rh/Rh and W/Rh in proportion to the atomic number of the target-filter. In addition, in phantom without implant a reduction in dose was seen when compared to the phantom with implant. The organ dose was highest in the lens except for the breast on the examination side regardless of the presence or absence of the implant. These results may contribute to use basic data for the diagnostic reference level of breast plastic surgery patients.

Radiological Safety Assessment of Transporting Radioactive Wastes to the Gyeongju Disposal Facility in Korea

  • Jeong, Jongtae;Baik, Min Hoon;Kang, Mun Ja;Ahn, Hong-Joo;Hwang, Doo-Seong;Hong, Dae Seok;Jeong, Yong-Hwan;Kim, Kyungsu
    • Nuclear Engineering and Technology
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    • 제48권6호
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    • pp.1368-1375
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    • 2016
  • A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea. We considered two kinds of wastes: (1) operation wastes generated from the routine operation of facilities; and (2) decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incidentfree (normal) transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day

  • Byun, Jaehoon;Choi, Woo Nyun;Kim, Hee Reyoung
    • Nuclear Engineering and Technology
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    • 제53권1호
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    • pp.273-281
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    • 2021
  • The radiological safety of the spent resin treatment facility with a14C treatment capacity of 1 ton/day was evaluated in terms of the external and internal exposure of worker according to operation scenario. In terms of external dose, the annual dose for close work for 1 h/day at a distance of more than 1 m (19.8 mSv) satisfied the annual dose limit. For 8 h of close work per day, the annual dose exceeded the dose limit. For remote work of 2000 h/year, the annual dose was 14.4 mSv. Lead shielding was considered to reduce exposure dose, and the highest annual dose during close work for 1 h/day corresponded to 6.75 mSv. For close work of 2000 h/year and lead thickness exceeding 1.5 cm, the highest value of annual dose was derived as 13.2 mSv. In terms of internal exposure, the initial year dose was estimated to be 1.14E+03 mSv when conservatively 100% of the nuclides were assumed to leak. The allowable outflow rate was derived as 7.77E-02% and 2.00E-01% for the average limit of 20 mSv and the maximum limit of 50 mSv, respectively, where the annual replacement of the worker was required for 50 mSv.

Assessment of Radiological Hazards in Some Foods Products Consumed by the Malian Population Using Gamma Spectrometry

  • Adama Coulibaly;David O. Kpeglo;Emmanuel O. Darko
    • Journal of Radiation Protection and Research
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    • 제48권2호
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    • pp.84-89
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    • 2023
  • Background: Food consumption is one of the most important routes for radionuclide intake for the public; therefore, there is the need to have a comprehensive understanding of the amount of radioactivity in food products. Consumption of radionuclide-contaminated food could increase potential health risks associated with exposure to radiation such as cancers. The present study aims to determine radioactivity levels in some food products (milk, rice, sugar, and wheat flour) consumed in Mali and to evaluate the radiological effect on the public health from these radionuclides. Materials and Methods: The health impact due to ingestion of radionuclides from these foods was evaluated by the determination of activity concentration of radionuclides 238U, 232Th, 40K, and 137Cs using gamma spectrometry system with high-purity germanium detector and radiological hazards index in 16 samples collected in some markets, mall, and shops of Bamako-Mali. Results and Discussion: The average activity concentrations were 9.8±0.6 Bq/kg for 238U, 8.7±0.5 Bq/kg for 232Th, 162.9±7.9 Bq/kg for 40K, and 0.0035±0.0005 Bq/kg for 137Cs. The mean values of radiological hazard parameters such as annual committed effective dose, internal hazard index, and risk assessment from this work were within the dose criteria limits given by international organizations (International Commission on Radiological Protection and United Nations Scientific Committee on the Effects of Atomic Radiation) and national standards. Conclusion: The results show low public exposure to radioactivity and associated radiological impact on public health. Nevertheless, this study stipulates vital data for future research and regulatory authorities in Mali.

Using RESRAD-BUILD for Potential Radiation Dose Estimation the Korea Research Reactor-1 When It Opens to the Public as a Memorial Hall

  • Lee, Sangbok;Yoon, Yongsu;Kim, Sungchul
    • International Journal of Contents
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    • 제16권2호
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    • pp.102-108
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    • 2020
  • The purpose of this study was to estimate and analyze the potential radiation dose that the future visitors and the cleaning staff will be exposed to when the KRR-1 reactor is converted into a memorial hall. The radiation doses were estimated using the RESRAD-BUILD software, where case, building, receptor, shielding, and source parameters were applied as the input data. Also, the basic data for the assessment of the radiation doses were determined in an indirect manner using the data on the waste generated during the decommissioning process of the reactor. The assessment results indicate that the potential radiation dose to the visitors and the cleaning staff will be less than 1 mSv, the annual dose limit for the general public. However, if anyone for a significant period of time is close to the reactor, the overall dose will increase. The radiation dose for the future visitors and the cleaning staff was determined to be lower than the annual dose limit for the general public. Given such a risk, systematic measures, such as periodic monitoring or limiting hours, are imperative.

RADIATION DAMAGE IN THE HUMAN BODY ACUTE RADIATION SYNDROME AND MULTIPLE ORGAN FAILURE

  • AKASHI, MAKOTO;TAMURA, TAIJI;TOMINAGA, TAKAKO;ABE, KENICHI;HACHIYA, MISAO;NAKAYAMA, FUMIAKI
    • Nuclear Engineering and Technology
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    • 제38권3호
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    • pp.231-238
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    • 2006
  • Whole-body exposure to high-dose radiation causes injury involving multiple organs that depends on their sensitivity to radiation. This acute radiation syndrome (ARS) is caused by a brief exposure of a major part of the body to radiation at a relatively high dose rate. ARS is characterized by an initial prodromal stage, a latent symptom-free period, a critical or manifestation phase that usually takes one of four forms (three forms): hematologic, gastrointestinal, or cardiovascular and neurological (neurovascular), depending upon the exposure dose, and a recovery phase or death. One of the most important factors in treating victims exposed to radiation is the estimation of the exposure dose. When high-dose exposure is considered, initial dose estimation must be performed in order to make strategy decisions for treatment as soon as possible. Dose estimation can be based on onset and severity of prodromal symptoms, decline in absolute lymphocyte count post exposure, and chromosomal analysis of peripheral blood lymphocytes. Moreover, dose assessment on the basis of calculation from reconstruction of the radiation event may be required. Experience of a criticality accident occurring in 1999 at Tokai-mura, Japan, showed that ARS led to multiple organ failure (MOF). This article will review ARS and discuss the possible mechanisms of MOF developing from ARS.

몬테칼로 모의모사를 이용한 유방성형술 환자의 유방선량평가 (Evaluation of Breast Dose in Mammography for Breast Implant Patient using a Monte Carlo Simulation)

  • 김지수;조용인;김정훈
    • 한국방사선학회논문지
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    • 제14권3호
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    • pp.253-259
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    • 2020
  • 유방촬영은 경제적이고 간편하며 미세석회화 검출에 효과적이라는 장점이 있으나, 유방은 감수성이 높은 장기이므로 확률적 영향에 의한 암 발생 위험을 동반한다. 이를 최소화하기 위해 정확한 유방 선량 평가가 필요하나, 현재 유방선량 평가는 일반여성들에게 한정되어 유방성형술 환자에게는 제한적이다. 본 연구는 유방성형환자의 정확한 선량 평가를 위하여 유방 보형물이 삽입된 모의피폭체를 구성하여 관전압에 따른 선량변화를 알아보고자 하였다. 그 결과, 유방 보형물이 있는 경우, 보형물이 없을 때의 선량보다 낮은 결과를 나타내었다. 검사 시 관전압 조건에 따른 선량 분포는 보형물의 유·무와 관계없이 관전압이 높아질수록 선량이 높아지는 양상을 보였다. 추후 본 연구를 통해 유방성형환자의 선량 관리 측면의 진단참고 수준 확립을 위한 기초적인 자료로서 활용 가능할 것으로 사료된다.