• Title, Summary, Keyword: 주민피폭선량 평가

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원자력시설의 정상운영시 주민피폭선량평가 입력자료의 개선

  • 전제근;이관희
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.437-438
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    • 2004
  • 원자력시설의 정상운영시 방사성물질이 기체 및 액체상의 형태로 소외로 배출되며, 일정기간별로 배출된 핵종별 총량을 이용하여 주민피폭선량 평가를 수행함으로써 규제요건의 준수 여부를 확인한다. 이러한 원자력시설 주변 주민피폭선량평가에 적용되고 있는 주요 입력자료인 음식물섭취자료 등은 1988년 원자력연구소의 현장조사, 실험, 문헌조사 등을 통하여 결정되었으나 시간이 지남에 따라 일부자료의 경우 최신경향을 반영할 수 있도록 개정이 요구된다.(중략)

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An Effects of Radiation Dose Assessment for Radiation Workers and the Member of Public from Main Radionuclides at Nuclear Power Plants (원전에서 발생하는 주요 방사성핵종들이 방사선작업종사자와 원전 주변주민의 피폭방사선량 평가에 미치는 영향)

  • Kim, Hee-Geun;Kong, Tae-Young;Jeong, Woo-Tae;Kim, Seok-Tae
    • Journal of Radiation Protection and Research
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    • v.35 no.1
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    • pp.12-20
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    • 2010
  • In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly, $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;and^{131}I$ are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.

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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    • 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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A Rapid Dose Assessment and Display System Applicable to PWR Accident (선량평가 및 Display시스템)

  • Moon, Kwang-Nam;Yook, Chong-Chul
    • Journal of Radiation Protection and Research
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    • v.13 no.2
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    • pp.67-77
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    • 1988
  • The necessity of developing a rapid dose assessment system has been emphasized for an effective emergency response of mitigation of off-site radiological consequences. A microcomputer program based on a rapid dose assessment model of the off-site radiological consequences is developed for various accdident sinarios for the Nuclear Power Plants in Korea. This model, which is consists of the user answering-question input format as a menu driven method and the output format of table and graphic types, is helpful to decision-making on Emergency Preparedness by being more rapidly able to implement the off-site dose assessment and to interpret the result.

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Comparison of the Regulatory Models Assessing Off-Site Radiological Dose due to the Routine Releases of Tritium (삼중수소의 환경방출에 따른 주민선량 규제모델의 비교)

  • Hwang Won-Tae;Kim Eun-Han;Han Moon-Hee;Choi Yong-Ho;Lee Han-Soo;Lee Chang-Woo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.2
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    • pp.125-133
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    • 2005
  • Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO) . A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEIIfTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment.

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Comparison of the Regulatory Models Assessing Off-Site Radiological Dose due to the Routine Releases of Tritium (삼중수소의 환경방출에 따른 주민선량 규제모델의 비교)

  • Hwang W. T.;Kim E. H.;Han M. H.;Choi Y. H.;Lee H. S.;Lee C. W.
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.464-473
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    • 2005
  • Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO). A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEWTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment.

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Research on the Transfer Factor for $C^{14}$ Ingestion Dose Evaluation in PWR plant (PWR 발전소에서 $C^{14}$ 섭취선량 평가를 위한 전이계수 연구)

  • Kim Soong-Pyung;Han Young-Ok;Park Kyeong-Rok
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • pp.476-484
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    • 2005
  • This paper is to evaluate rather correctly $C^{14}$ ingestion dose that inhabitants around PWR plants can receive, and draw how to apply TF(Transfer Factor) to evaluate dose by the ingestion of animal products. For this, in this paper, dose assessment and analysis about existing materials related to TF were carried out, and the methodology to present TF was based on dose assessment and analysis result. The ingestion dose calculated using TFs presented by CSA and KEPRI was high or equal compared with SAM(Specific Activity Model) which is the most conservative, on the other hand, TFs given by NEC did not consider the effect according to volume change of animal at all, Therefore, it is judged that models used in the existing codes to asses the $C^{14}$ concentration into animal products must be improved to apply fundamentally hybrid model using transfer factors, that transfer factor on each animal products have to be developed through experiment for applying to our county.

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Effective Dose Equivalent due to Inhalation of Indoor Radon-222 Daughters in Korea (한국인의 라돈-222 자핵종 호흡 실효선량당량 평가)

  • Chang, Si-Young;Ha, Chung-Woo;Lee, Byoung-Hun
    • Journal of Radiation Protection and Research
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    • v.16 no.1
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    • pp.1-13
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    • 1991
  • Effective dose equivalents resulting from inhalation of indoor radon-222 daughters at 12 residential areas in Korea were assessed by a simple mathematical lung dosimetry model based on the measurements of long-term averaged radon concentrations at 340 dwellings. The long-term averaged indoor radon-222 concentrations and corresponding eqilibrium equivalent radon $concentration(EEC_{Rn})$ measured by passive time-integrating CR-39 radon cups are in the range of $33.82{\sim}61.42Bq/m^3(median\;:\;48.90Bq/m^3)$ and of $13.53{\sim}24.57Bq/m^3(median\;:\;19.55Bq/m^3)$, respectively. The effective dose equvalent conversion factor for the exposure to unit $EEC_{Rn}$ derived in this study was estimated $1.07{\times}10^{-5}mSv/Bq\;h\;m^{-3}$ for a reference adult and agreed well with those recommended by the ICRP and UNSCEAR. The annual average dose equivalent to the lung $(H_{LUNG})$ from inhalation exposure to measured $EEC_{Rn}$ was estimated to be 20.90 mSv and resulting effective dose $equivalent(H_E)$ was to be 1.25 mSv, which is about 50% of the natural radiation exposure of 2.40 mSv/y to the public reported by the UNSCEAR.

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