• Title/Summary/Keyword: 일반인 피폭

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Trends and Issues in Metabolism and Dosimetry for Tritium Intake (삼중수소 피폭방사선량 평가의 경향과 이슈에 대한 고찰)

  • Kim, Hee-Geun;Kong, Tae-Young;Jeong, Woo-Tae
    • Journal of Radiation Protection and Research
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    • v.36 no.2
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    • pp.99-106
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    • 2011
  • Tritium is the one of the most important radionuclide for workers in nuclear power plants (NPPs) and the public, from the dosimetric point of view. Humans are likely to have internal radiation exposure by tritium inhalation. Radiation exposure by tritium accounts for approximately 7% and 60~90% of the total radiation exposure of NPP workers and the public during normal operation, respectively. Thus, many researches have been conducted to estimate the internal dose by tritium precisely in the world. In terms of tritium dosimetry, this paper provides the current status of research for tritium metabolism and dosimetry.

A Study on Exposure to radiation of the patient who visited an emergency room at a University Hospital (한 대학병원 응급실에 방문한 환자의 방사선 피폭에 관한 연구)

  • Ahn, Buyung-Ju;Lee, Sang-Bock;Lee, Jun-Haeng
    • Journal of the Korean Society of Radiology
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    • v.1 no.3
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    • pp.23-34
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    • 2007
  • To find how much radiation was exposed the patients who visit emergency room, a measurement study was made for radiation amount toward 200 patients selected randomly among visitors to an emergency room in a university hospital from March 16 to 31st, 2006. The results are as follows ; 1. Among the subjects 50 person(25.0%) were transferred from other hospitals, 24 persons(8.3) come after traffic accident, 50 persons for other accident and 76 persons for general medical care. 2. The average frequency of X-ray taking was calculated as 6.4 time per person among transferred patients, 14.5 times per person among patients with traffic accident and 2.6 times per person among general medical care. 3. The radiation exposure amount by kind of X-ray showed 28.9mGyfor general X-ray diagnosis, 84.2mGy for CT scanning and 1.02mGy for other special radiation study. 4. Average radiation exposure amount was calculated as 24.6mGy by transferred patients, 55.2mGy by patients with traffic accident, 17.1mGy by patients with other accidents and 17.0mGy by general patients. 5. Through the comparison of radiation exposure amount among to subject with maximum allowance threshold by International Commission on X-ray Radium Protection, transferred patients exceeded 6 times than allowance in whole body except extremities and joints, blood forming organ, reproductive system, vitreous body of eye, bone, thyroid gland, skin and etc, Patient suffered from traffic accidents were exposed 10 times more than allowance. In conclusion, the radiation exposure amount during X-rat diagnosis re too much and exceeded allowance standard by International Commission on X-ray Radium Protection. So further study and preventive measure to decrease radiation exposure by patients who visit emergency room.

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Analysis of Changed Bio-Signal to Radiation Exposure of Nuclear Medicine Worker (핵의학 종사자의 방사선 피폭에 따른 생체신호 변화 분석)

  • Lee, Hwun-Jae;Lee, Sang-Bock
    • Journal of Radiation Protection and Research
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    • v.32 no.1
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    • pp.27-34
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    • 2007
  • In this paper, We are evaluated about bio-signal between general workers and nuclear medicine workers which is more radiation exposure relatively. In order to reciprocal evaluated two group, we experimented nuclear medicine workers in Chung-Buk National University Hospital at department of nuclear medicine and worker in Chon-Nam National University Hospital at CT room, general radiographic room, medical recording room, receipt room, general office room. Used of experimental Equipments as follows, for a level of radiation measurement by pocket dosimeter which made by Arrow-Tech company, for heart rate and blood pressure measurement by TONOPORT V which made by GE medical systems company, for heat flux and skin temperature and energy expenditure measurement by Armband senseware 2000 which made by Bodymedia company. Result of experiment obtains as follows: 1) Individual radiation exposure is recorded 3.05 uSv at department of nuclear medicine and order as follows CT room, general radiograpic room, medical recording room, receipt room, general office room. Department of nuclear medicine more 1.5 times than other places. 2) Radiation accumulated dose is not related to Heat flux, Skin temperature, Energy expenditure. 3) Blood pressure is recorded equal to nuclear medical workers, general officer, general people about systolic blood pressure and diastolic blood pressure. Compared to blood pressure between nuclear medical works which is more radiation exposure and other workers was not changed. Consequently, more radiation exposed workers at nuclear medicine field doesn't have hazard.

A Study on the Radiation Dose Managements in the Nuclear Medicine Department (핵의학과에서 방사선 피폭관리 실태에 대한 조사 연구)

  • Lim, Chang-Seon;Kim, Se-Heon
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.10 no.7
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    • pp.1760-1765
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    • 2009
  • After administration of a radiopharmaceutical, the patient remains radioactive for hours or even days, representing a source of potential radiation exposure. Thus, including the personnel who are occupationally exposed to ionizing radiation, radiation exposure must be managed for members of the public, in particular for people accompanying patients. In this study we investigated radiation exposure dose management in the nuclear medicine departments at seven general hospitals. Two of them had no radiation safety considerations for patient transporters, sanitation workers and the like. And they all were careless of radioprotection for people accompanying patients. The average dose rate to people accompanying patients from radioactive patients just before a bone scan was 25.60 ${\mu}$Sv h-1. This is higher than 20 ${\mu}$Sv $h^{-1}$which is the annual public dose limit for temporary use. Therefore radiation dose measurement and risk assessment of patient transporters, sanitation workers and the like should be performed. And the nuclear medicine technologist should provide advices on the radiation safety to patient transporters, sanitation workers, people accompanying patients and so on. To ensure the radiation safety for people accompanying patients, it is required to restrict the patient's access to his relatives, friends and other patients or isolate patients.

A Preliminary Establishment of Dose Constraints for the Member of Public Taking into Account Multi-unit Nuclear Power Plants in Korea (국내 복수호기 원전 운영을 고려한 일반인 선량제약치 설정에 대한 고찰)

  • Kong, Tae-Young;Choi, Jong-Rack;Son, Jung-Kwon;Kim, Hee-Geun
    • Journal of Radiation Protection and Research
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    • v.37 no.3
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    • pp.129-137
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    • 2012
  • In the 2007 recommendation, the ICRP evolves from the previous process-based system of practices and intervention to the system based on the characteristics of radiation exposure situation. In addition, ICRP recommends the application of source-related dose constraints under the planned exposure situation as a tool for the optimization of protection to workers and the member of public. In this study, the analysis of radioactive effluents from Korean nuclear power plants and the public dose assessment were conducted in reference with the use of dose constraints. Finally, the measure to implement the dose constraints for the member of public was suggested taking into account multi-unit reactors operating at a single site in Korea.

Development of Personal Dosimeter (개인 피폭선량 측정 시스템 개발)

  • Kwon, S.G.;Yi, U.K.;Lim, Hun;Sohn, C.H.;Kim, J.S.;Lee, C.J.
    • Proceedings of the KIEE Conference
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    • 2000.11d
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    • pp.724-726
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    • 2000
  • 일반적으로 개인방사선감시에 열형광선량계와 필름배지가 공식 개인선량계로 이용되어 왔고 현재까지도 가장 보편적으로 사용되고 있다. 하지만 최근에는 Si 다이오드와 G-M관을 이용한 능동형 개인피폭선량계가 개발 보급되고 있다. 개인피폭선량계는 누적선량을 실시간으로 알 수 있다는 장점을 가지고 있을 뿐만 아니라 선량률에 관한 정보도 제공하므로 높은 비용부담에도 불구하고 피폭관리의 용이함으로 인해 주목을 받고 있다. 따라서 본 연구는 수입에 의존해 온 개인피폭선량계를 대체하기 위해 반도체형 방사선 검출기를 설계하여 다양한 서비스를 부가할 수 있는 개인피폭선량계를 자체개발고, 선량계의 운영 및 판독을 위한 장치를 개발하였다.

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Variation Analysis of Distance and Exposure Dose in Radiation Control Area and Monitoring Area according to the Thickness of Radiation Protection Tool Using the Calculation Model: Non-Destructive Test Field (계산 모델을 활용한 방사선방어용 도구 두께에 따른 방사선관리구역 및 감시구역의 거리 및 피폭선량 변화 분석 : 방사선투과검사 분야 중심으로)

  • Gwon, Da Yeong;Park, Chan-hee;Kim, Hye Jin;Kim, Yongmin
    • Journal of the Korean Society of Radiology
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    • v.14 no.3
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    • pp.279-287
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    • 2020
  • Recently, interest in radiation protection is increasing because of the occurrence of accidents related to exposure dose. So, the nuclear safety act provides to install the shields to avoid exceeding the dose limit. In particular, when the worker conducts the non-destructive testing (NDT) without the fixed shielding structure, we should monitor the access to the workplace based on a constant dose rate. However, when we apply for permits for NDT work in these work environments, the consideration factors to the estimation of the distance and exposure dose are not legally specified. Therefore, we developed the excel model that automatically calculates the distance, exposure dose, and cost if we input the factors. We applied the assumption data to this model. As a result of the application, the distance change rate was low when the thickness of the lead blanket and collimator is above 25 mm, 21.5 mm, respectively. However, we didn't consider the scattering and build-up factor. And, we assumed the shape of the lead blanket and collimator. Therefore, if we make up for these limitations and use the actual data, we expect that we can build a database on the distance and exposure dose.

An Improved Methodology of Monetary Values of the Unit Collective Dose for Intervention Against Long-Term Exposure Following a Nuclear Accident (원자력 사고후 장기피폭에 대한 개입을 위한 피폭선량 금전가 산정의 개선된 방법론)

  • Hwang, Won-Tae;Kim, Eun-Han;Suh, Kyung-Suk;Choi, Young-Gil;Han, Moon-Hee
    • Journal of Radiation Protection and Research
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    • v.27 no.2
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    • pp.77-80
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    • 2002
  • A more practice approach for the determination of monetary values of the unit collective dose for intervention against long-term exposure following a nuclear accident was proposed. In addition, she monetary values of the unit collective dose estimated from the proposed approach were compared with those estimated from the previous model, which are derived from assumptions of routine exposure and the same values are applied in a nuclear accident without modification, using Korean economic data. The monetary values based on the proposed approach showed a distinct difference depending on inequity in the distribution of individual doses. The discounting rate was also an important factor in determination of monetary values of the unit collective dose.

Enhancement of Image Quality Using Detector Filter (검출기 필터를 이용한 화질의 향상)

  • Lim, Jong-Nam;Kim, Hyung-Tae;Kim, Min-Hye;Chon, Kwon Su
    • Journal of the Korean Society of Radiology
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    • v.10 no.6
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    • pp.451-456
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    • 2016
  • Radiation dose to patient is unavoidable when diagnosis is carried out using X-ray. Radiation diagnosis using dual energy X-ray was examined to verify the possibility of medical applications by SNR and image scoring. The dual energy X-ray was realized by combining together two image plates and filter of 0.5 mm thick Cu or Al. Under one X-ray exposure, contrast enhanced image was obtained using two images of image plates. The enhanced image showed higher SNR and image score compared to the first image which was the image recorded with the first image plate. The dual energy X-ray technique would be a very useful method for obtaining higher SNR image and for realizing very low dose, and could be applied to medical applications.

Calculation of Route Doses for Korean-based International Airline Routes using CARI-6 and Estimation of Aircrew Exposure (CARI-6를 이용한 국제선 노선별 선량 및 항공승무원의 피폭선량 평가)

  • Hong, J.H.;Kwon, J.W.;Jung, J.H.;Lee, J.K.
    • Journal of Radiation Protection and Research
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    • v.29 no.2
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    • pp.141-150
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    • 2004
  • Dose rate characteristics of cosmic radiation field at flight altitudes were analyzed and the route doses to the personnels on board due to cosmic-ray were calculated for Korean-based commercial international airline routes using CARI-6. Annual individual doses to aircrew and the collective effective dose of passengers were estimated by applying the calculated route doses to the flight schedules of aircrew and the air travel statistics of Korea. The result shows that the annual doses to aircrew, around 2.62 mSv, exceed the annual dose limit of public and are comparable to doses of the group of workers occupationally exposed. Therefore it is necessary to consider the frequent flyers as well as the aircrew as the occupational exposure group. The annual collective dose to 11 million Korean passengers in 2001 appeared to be 136 man-Sv. The results should be modified when the dose rates of cosmic radiation at high altitude are revised by taking into account the changes in the radiation weighting factors for protons and neutrons as given in ICRP 92.