• Title/Summary/Keyword: 피폭 방사선량

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The BIDAS Program : Bioassay Data Analysis Software for Evaluating Radionuclide Intake and Dose (BIDAS프로그램 : 방사성 핵종의 섭취량과 선량 평가용 생물학적분석 자료 해석 소프트웨어 프로그램)

  • Tae-Yong Lee;Jong-Kyung Kim;Jong-Il Lee;Si-Young Chang
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.2 no.2
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    • pp.113-124
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    • 2004
  • A computer software program, called BIDAS (BIoassay Data Analysis Software) is developed to interpret the bioassay measurement data in terms of intakes and the committed effective dose using the human respiratory tract model (HRTM), gastrointestinal tract (GI-tract) model and biokinetic models currently recommended by the International Commission on Radiological Protection (ICRP) to describe the behavior of the radioactive materials within the body. The program consists of three modules; first, a database module to manage the bioassay data, second, another databasee module to store the predicted bioassay quantities of each radionuclide and finally, a computational module to estimate the intake and committed effective dose calculated with the bioassay quantity measurement values from either an acute or chronic exposure of the radionuclies within the body. This paper describes the features of the program as well as the quality assurance check results of the BIDAS software program.

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A Study of Targetry Activation and Dose Analysis of PET Cyclotron Using Monte Carlo Simulation (몬테카를로 모의 모사를 이용한 의료용 사이클로트론의 Targetry 방사화 및 피폭선량 분석)

  • Jang, Donggun;Kim, Dong hyun
    • Journal of the Korean Society of Radiology
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    • v.12 no.5
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    • pp.565-573
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    • 2018
  • Cyclotron for medical purposes generates nuclear reaction by accelerating protons in high speed, in order to produce radiopharmaceuticals, and unnecessary neutrons are generated through such nuclear reaction. Neutrons cause activation in the parts of cyclotron which then cause exposure to radiation for people working in the field. This study, in that regard, aims to analyze exposure level by finding out the degree of activation of aluminum body, silver body, and havar foil which are the parts of Targetry where the nuclear reaction takes place. The results of the experiment showed that aluminum body and silver body had no problems re-using them as the energy and half-life of activated nuclides were small and short, making the affect on the people working in the field extremely low. However for havar foil, its activated nuclides had a high level of energy which resulted in high level of affect to the people working in the field. The activation factors of the cyclotron were analyzed, and the results showed that the Havar foil was activated the most among the targetry parts, and greatly exposed workers due to regular replacement, and needed special management as radioactive waste.

Comparisons and Measurements the Dose Value Using the Semiconductor Dosimeter and Dose Area Product Dosimeter in Skull, Chest and Abdomen (두개부, 흉부, 복부검사 시 반도체 선량계와 면적 선량계를 이용한 선량 값의 측정 및 비교)

  • Kim, Ki-Won;Son, Jin-Hyun
    • Journal of radiological science and technology
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    • v.38 no.2
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    • pp.101-106
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    • 2015
  • Recently, There has been a growing interests in exposure dose to the patient who take a examination using radiation. The radiological technologists should be concerned about the exposure dose to patients and make an efforts to reduce the patient dose without decreasing the image quality. In the case of foreign, the exposure dose of general X-ray examination have been managed by standard value of exposure dose using dose area product (DAP) and entrance surface dose (ESD) dosimeter. This study is to compare DAP and ESD in skull anterior posterior (AP), chest posterior anterior (PA), and abdomen AP projections of phantom by using DAP and ESD dosimeter. In the results, there were no differences between DAP and ESD dosimeter.

Evaluation of Radiation Exposure to Medical Staff except Nuclear Medicine Department (핵의학 검사 시행하는 환자에 의한 병원 종사자 피폭선량 평가)

  • Lim, Jung Jin;Kim, Ha Kyoon;Kim, Jong Pil;Jo, Sung Wook;Kim, Jin Eui
    • The Korean Journal of Nuclear Medicine Technology
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    • v.20 no.2
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    • pp.32-35
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    • 2016
  • Purpose The goal for this study is to figure out that medical staff except Nuclear Medicine Department could be exposed to radiation from the patients who take Nuclear Medicine examination. Materials and Methods Total 250 patients (Bone scan 100, Myocardial SPECT 100, PET/CT 50) were involved from July to October in 2015, and we measured patient dose rate two times for every patients. First, we checked radiation dose rate right after injecting an isotope (radiopharmaceutical). Secondly, we measured radiation dose rate after each examination. Results In the case of Bone scan, dose rate were $0.0278{\pm}0.0036mSv/h$ after injection and $0.0060{\pm}0.0018mSv/h$ after examination (3 hrs 52 minutes after injection on average). For Myocardial SPECT, dose rate were $0.0245{\pm}0.0027mSv/h$ after injection and $0.0123{\pm}0.0041mSv/h$ after examination (2 hrs 09 minutes after injection on average). Lastly, for PET/CT, dose rate were $0.0439{\pm}0.0087mSv/h$ after examination (68 minutes after injection on average). Conclusion Compared to Nuclear Safety Commission Act, there was no significant harmful effect of the exposure from patients who have been administered radiopharmaceuticals. However, we should strive to keep ALARA(as low as reasonably achievable) principle for radiation protection.

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A study on the Radiation exposure of simple abdomen x-ray in Radiography (복부 단순 X선검사시 피복 선량에 관한 연구)

  • Ko In Ho;Lee Kyung Sung;Shin Dong Yong
    • Journal of The Korean Radiological Technologist Association
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    • v.27 no.2
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    • pp.57-65
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    • 2001
  • This study was performed to measure about exposure dose during simple abdomen x-ray Radiography. The exposure dose was measured by PDD, surface dose, percentage scatter dose, respectively. The result was as followed: 1. When tube voltage were increased wi

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Analysis of Parameters for the Off-Site Dose Calculation Due to HTO, oBT, and Radioactive Carbon Ingestion (국내 원자력발전소 주변 삼중수소 및 $^14C$ 섭취선량 평가 경로인자 분석)

  • 이갑복;정양근;방선영;엄희문
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.361-367
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    • 2004
  • For assessment of tritium and radiocarbon ingestion dose to off site individuals, water, hydrogen, and carbon content of main farm produce of Korea were investigated to replace the existing data in K-DOSE60, the Offsite Dose Calculation Manual (ODCM) of Korea Hydro & Nuclear Power Co. Ltd, (KHNP). Main items and weighting factors of farm produce were determined with the nationwide food intake data in 2001, 2002. Main farm produce were sampled around Kori, Wolsong, Ulchin, Younggwang nuclear power sites, Content of each produce was multiplied by weighting factor and summed up to make the weighted mean group value For grains, water, hydrogen, and carbon content was not much different from the existing data currently used in K-DOSE60, but root vegetables had 3.5 times more hydrogen, and leafy vegetables and fruits had 0.7∼1.3 times more or less water, hydrogen, and carbon contents than K-DOSE60.

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Medical Radiation Exposure Dose of Workers in the Private Study of the Job Function (의료기관 방사선 종사자의 직무별 개인피폭선량에 관한 연구)

  • Kang, Chun-Goo;Oh, Ki-Baek;Park, Hoon-Hee
    • The Korean Journal of Nuclear Medicine Technology
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    • v.15 no.2
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    • pp.3-12
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    • 2011
  • Purpose: With increasing medical use of radiation and radioactive isotopes, there is a need to better manage the risk of radiation exposure. This study aims to grasp and analyze the individual radiation exposure situations of radiation-related workers in a medical facility by specific job, in order to instill awareness of radiation danger and to assist in safety and radiation exposure management for such workers. Materials and Methods: From January 1, 2010 December 31, 2010, medical practitioners working in the radiation is classified as a regular personal radiation dosimetry, and subsequently one year 540 people managed investigation department to target workers, dose sectional area, working period, identify the job function-related tasks for a deep dose, respectively, the annual average radiation dose were analyzed. Frequency analysis methods include ANOVA was performed. Results: Medical radiation workers in the department an annual radiation dose of Nuclear and 4.57 mSv a was highest, dose zone-specific distribution of nuclear medicine and in the 5.01~19.05 mSv in the high dose area distribution showed departmental radiation four of the annual radiation dose of Nuclear and 7.14 mSv showed the highest radiation dose. More work an average annual radiation dose according to the job function related to the synthesis of Cyclotron to 17.47 mSv work showed the highest radiation dose, Gamma camera Cinema Room 7.24 mSv, PET/CT Cinema Room service is 7.60 mSv, 2.04 mSv in order of intervention high, were analyzed. Working period, according to domain-specific average annual dose of radiation dose from 10 to 14 in oral and maxillofacial radiology practitioners as high as 1.01~3.00 mSv average dose showed the Department of Radiology, 1-4 years, 5-9 years, respectively, 1.01 workers~8.00 mSv in the range of the most high-dose region showed the distribution, nuclear medicine, and the 1-4 years, 5-9 years 3.01~19.05 mSv, respectively, workers of the highest dose showed the distribution of the area in the range of 10 to 14 years, Workers at 15-19 3.01~15.00 mSv, respectively in the range of the high-dose region were distributed. Conclusion: These results suggest that medical radiation workers working in Nuclear Medicine radiation safety management of the majority of the current were carried out in the effectiveness, depending on job characteristics has been found that many differences. However, this requires efforts to minimize radiation exposure, and systematic training for them and for reasonable radiation exposure management system is needed.

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