• Title/Summary/Keyword: 피폭선량 추정

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Estimated Exposure Dose and Usage of Radiological Examination of the National Health Screening (국가건강검진의 방사선검사 이용량 및 피폭선량 추정)

  • Gil, Jong Won;Park, Jong Hyock;Park, Min Hui;Park, Chan Young;Kim, So Young;Shin, Dong Wook;Kim, Won Dong
    • Journal of Radiation Protection and Research
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    • v.39 no.3
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    • pp.142-149
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    • 2014
  • Korea conducts a national health screening program to improve and check-up on public health and in recent years, the screening usage has been increased. Given the increased screening usage for radiographic exams, this study predicts the frequency of using radiographic exams and the exposure dose. This study estimates the usage of radiographic exams by isolating radiographic exams from the 2011 analysis of the national health insurance corporation, and estimates the public exposure dose by applying each procedure's dose table from UNSCEAR 2008. As a result of the analysis, in the 2011 National Health Screening, the average exposure dose per person is assumed to be 0.57 mSv, and depending on the type of screening program from the radiographic exam, an examinee could be exposed to between 0.2 mSv and 11.081 mSv. The frequency of using radiographic exposure was found to be 16,005,914 and the exposure dose was 6,311.76 person-Sv. The most frequent exam is the Chest X-ray, which was performed 1,070,567 (69.17%), and the UGI has the highest exposure dose at 5,217.94 person-Sv (82.67%). The outcome is categorized based on gender and age, excluding those under 39 years old. In all age groups, the screening usage and exposure dose are higher in females than in males. In particular, females between 50 and 54 years old have the highest screening usage (1,674,787, 10.5%) and exposure dose (701.59 person-Sv, 11.1%). As UGI accounts for 82.76% of procedures, except when done for medical purposes, if the government supports a voluntary UGI exam (which includes the UGI exam in the National Screening Program) or abolishes it completely, as seen overseas, the cost-effectiveness and validity of the UGI exam, as well as the exposure dose from the National Screening Program will all decrease significantly.

Study on The Planning and Operation of Training Education in Radiologic Science for Reduced x-ray Exposure (방사선(학)과 실습교육에서 X선 피폭 감소를 위한 운영방법에 대한 연구)

  • Kil, Jong-Won;Park, Jung-Ho;Kim, Yong-Gwon
    • Journal of the Institute of Electronics and Information Engineers
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    • v.51 no.12
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    • pp.174-179
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    • 2014
  • In this study, we measure the radiation dose for every experiments performed during the training education in radiologic science and estimate the radiation dose to each participant in the training education to propose a safe curriculum including operation of the training education. In this paper, we optimized the three parameters and the results show the dramatically reduced radiation dose to each participant. The proposed arrangement of the subjects and operation of the training education will be very helpful to reorganize the curriculum and the subject operation and will protect the students from the radiation dose.

Survey of CT Practice and Collective Effective Dose Estimation (CT검사건수 및 CT검사에 의한 집단 실효선량의 추정)

  • Lee, Man-Koo;Lim, Cheong-Hwan
    • Journal of radiological science and technology
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    • v.33 no.3
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    • pp.231-237
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    • 2010
  • Computed tomography (CT) has been established as an important diagnostic tool in clinical medicine and has become a major source of medical exposure. A nationwide survey regarding CT examinations was carried out in 2007. Thanks to the appeasement policy regulating the import of CT scanners, there are 1,825 CT scanners across the country as of the end of March 2010, which means that we have 36.8 CT scanners per one million people. The annual number of examinations was 3.29 million, the number of examinations per 1000 population was 68. The most part of examinations was abdomen and pelvis. and the collective effective dose was in these parts. The effective dose per one population was evaluated as 0.952 mSv.

Chromosomal Aberrations Induced by in Vitro Irradiation of $^{131}I$ ($^{131}I$의 체외 방사선조사에 의한 염색체이상)

  • Kim, Eun-Sil;Kim, Myung-Seon;Seo, Doo-Seon;Jeong, Nae-In;Rho, Seung-Ik;Lee, Jae-Yong;Kim, Chong-Soon;Han, Seung-Soo;Kim, Hee-Geun;Kang, Duck-Won;Song, Myung-Jae
    • The Korean Journal of Nuclear Medicine
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    • v.28 no.1
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    • pp.133-140
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    • 1994
  • Recently, there are many considerations and studies on biological effects of radiations in radiation workers, as well as in accidentally or therapeutically irradiated persons. The most practical and reliable method of dosimetry for radiation accidents is the scoring of gross chromosomal aberrations in human lymphocytes (Ydr) as a biological dosimetry. By the way, although usual doses of $^{131}I$ administered therapeutically for thyroid cancer are ranging from 100 mCi to 200 mCi, there are differences of absorbed doses and Ydr, ranging from 0.004 to 0.04, on equally administered $^{131}I$ due to variations in metabolic characteristics, stage of tumors and physical status of subjects. In this study, We exert to obtain the dose-response relationships of $^{131}I$, as a good guide to evaluating acute effects of accidental irradiations and radiation induced leukemia or solid tumor, by in vitro induction of chromosomal aberrations. we studied the relationship between radiation dose (D) and the frequency of chromosomal aberrations (Ydr) obserbed in peripheral lymphocytes that were irradiated in vitro with $^{131}I$ at doses ranging from 0.05 to 6.00 Gy. By scoring cells with unstable chromosomal aberrations (dicentric chromosomes and ring chromosomes) we obtained this linear-quadratic dose response equation Ydr=0.064351 $D^2$-0.13143 D+0.045684 This dose-response relationship may be useful for evaluating acute and chronic $^{131}I$ induced biological effects.

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일본의 환경방사능 감시체제

  • 한국원자력산업회의
    • Nuclear industry
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    • v.7 no.5 s.51
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    • pp.78-81
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    • 1987
  • 환경방사선에 의한 전신피폭선량중 대부분은 자연방사선에 의한 것이며 또 지질의 차에 의한 지역차도 커서 이 레벨을 파악하는 것은 국민선량을 추정$\cdot$평가하는데 있어서 중요하다.

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Studies on the Reference Korean and Estimation of Radiation Exposure Dose - PHYSICAL STANDARD AND ESTIMATION OF INTER-EXTERNAL RADIATION EXPOSURE DOSE - (표준한국인(標準韓國人)의 최대허용(最大許容) 피폭선량(被曝線量) 설정(設定)에 관한 연구(硏究) - 체위(體位) 및 내(內).외부(外部) 피폭선량(被曝線量) 추정(推定) -)

  • Kim, Yung-J.;Lee, Kang-S.;Chun, Ki-J.;Kim, Jong-B.;Chung, Gook-H.;Kim, Sam-R.
    • Journal of Radiation Protection and Research
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    • v.7 no.1
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    • pp.1-10
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    • 1982
  • For the purpose of establishment of Reference Korean and estimation of internal and external exposure doses in the Reference Korean, we have surveyed reference values for Koreans, such as physical standards including height, weight and body surface area, food consumption rate of daily intake of radioactive substances and exposure dose from natural radiation. The results obtained are as follows: 1) The age group of the Reference Korean ranged from 20 to 30 years old in both sexes. The height, weight and surface area of the body of the Reference Korean are 167cm, 61kg and $1.67m^2$ in male and 155cm, 51kg and $1.51m^2$, respectively in female. 2) The food consumption of the Korean is 812.8g (669.6g of vegetable food and 143.2g of animal food) per capita per day. 3) Koreans are taken about 1,200 pCi of radioactive substances(${\beta}$-ray) per capita per day. 4) The external and internal radiation exposure doses of the Korean are estimated to be 127 mrem and 8 mrem per year, respectively. However, it is believed that these values will be modified upon the addition of data collection.

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A Measurement of Exposure Dose for Patient Transporter (환자 이송원의 피폭선량 측정)

  • Song, Chaerim;Lee, Wanghui;Ahn, Sungmin
    • Journal of the Korean Society of Radiology
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    • v.13 no.3
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    • pp.433-438
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    • 2019
  • The medical institutions use radiation generating devices and radioactive isotopes to diagnose and treat patients. The patient transporter performs work in an environment that is more likely to be exposed to radiation when compared with the general public, such as inevitably entering the radiation management area for patient transfer, or transferring the isotope-administered patient at a short distance. For this reason, we conducted a study to determine the degree of exposure of the patient transporter. The 12 patient transporters working at Incheon A General Hospital are eligible. From April 1, 2019 to April 30, 2019, the dosimeter was used in the chest for one month and the accumulated dose was measured. The dosimeter used was a Optically Stimulated Luminescence Dosimetry (OSLD) and the dose reading was OSLD Microstar Reading System. As a result of cumulative dose measurement for one month, the average of the deep dose was 0.13 mSv and the surface dose was 0.13 mSv, and the cumulative dose for one month was multiplied by 12 to estimate the cumulative dose expectation As a result, the average of the deep dose and the surface dose were 1.52 mSv and 1.51 mSv, respectively. It is necessary to classify the patient transporter as a frequent visitor in order to measure and manage the exposure dose, increase the knowledge of protection against radiation through education and training, and prevent radiation trouble through medical examination.

Cytogenetic and Medical Examination Report of Accidental Exposure of Nuclear Power Plant Worker using Multiple Assays (원자력 발전소 피폭자 건강영향평가 사례보고)

  • Lee, Jung-Eun;Yang, Kwang-Hee;Jang, Yun-Kun;Jeong, Mee-Seon;Kim, Chong-Soon;Jin, Young-Woo
    • Journal of Radiation Protection and Research
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    • v.32 no.3
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    • pp.111-115
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    • 2007
  • A deuterium oxide leakage accident occurred on October 4, 1999, at nuclear power plant in Korea. The concentration of tritium in air increased and 22 workers were exposed by tritium at that time. It is well known that tritium causes internal exposure. Therefore, we examined complete blood cell count, physical and biological dosimetry fur 13 workers among whole 22 workers to check the health effect and to evaluate the dose estimation of tritium exposure. The leukocyte count test, one of general blood test, was normal. The estimated doses were 0 - 4.44 mSv by physical dosimetry and 0-37 mGy by biological dosimetry. This dose does not exceed radiation dose limit, and the clinical symptoms of the exposed workers were not shown. The consistency between clinical sign and estimated dose means that physical and biological dosimetry were very useful especially in accident evaluation.

The Development and It′s Characteristics of New Film Dosimetry Algorithm for Personal Dosimetry (개인피폭 선량 측정을 위한 필름 배지 선량계의 새로운 알고리즘 개발 및 특성)

  • 이병용;장혜숙;봉정균;권수일
    • Progress in Medical Physics
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    • v.6 no.2
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    • pp.35-40
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    • 1995
  • Purpose: We have developed new film dosimetry algorithm for personal dosimetry and examined its characteristics. Materials and methods: Agfagaevart personal monitoring 2/10 films are used. Films which are in the film badges filtered with Cu 0.3mm, plastic 1.5mm, Aluminum 0.6mm and tin 0.8mm, were exposed by standard dosimetry laboratory. Irradiated energy categories are ANSI N13.1l Category III, and IV. Manual type film precessor and X-rite film densitometor was used. Filtered densities to energy relations and does to transformed densities relations can be obtained ofter transformation of H&D curves to linear shape by polynomal fitting. Reults : Personal dose be determined within 25% error for category m and 15% for category IV. And we are able to evaluate the exposed energy. Conclusion : New algorithm developed in this study is good for personal dosimetry within 30% error range for catergory III and IV. It is expectd to be complete personal dosimetry algorithm with further study for categrory, I, Dand II V.

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