• 제목/요약/키워드: Radiation Limits

검색결과 177건 처리시간 0.023초

Derived Limits for Radiological Protection Against ionizing Radiation Based on ICRP-60 Recommendations

  • Jang, Si-Young;Lee, Byung-Soo
    • Nuclear Engineering and Technology
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    • 제32권4호
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    • pp.350-360
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    • 2000
  • In Korea, the dose limits are reduced and are set at the ICRP-60 iimits. However, derived limits tabulated as MPC in air and water are still specified in Notice No.98-12. There are some discrepancies between the primary dose limits and MPCs in air and water. Therefore, in order to accept ICRP-60 recommendations fully, derived limits such as ALI, DAC, ECL for radiological protection against ionizing radiation based on ICRP-60 recommendations were calculated using modified methods of those of 10 CFR part 20, dose limits and committed effective dose coefficients of the Basic Safety Standards of the IAEA. The derived limits in this study were also compared with those prescribed in 10 CFR part 20 as well as MPCs of Notice No. 98-12 in order to analyze the impact of implementing derived limits on nuclear facilities. ECLs in air and water for the control of radioactive discharge into the environment in this study are shown to have lower values (i.e. more conservative), for most part, than those in Notice No. 98-12. Especially, for uranium elements, ECLs in water are approximately a magnitude in the order of two lower than those in Notice No.98-12.

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중수로원전 방사성유출물 관리와 유도배출한계 설정방법에 대한 고찰 (Review on the Management for Radioactive Effluent and Methodology for Setting of Derived Release Limits at Pressurized Heavy Water Reactors in Korea)

  • 김희근;공태영;정우태;김석태
    • Journal of Radiation Protection and Research
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    • 제35권4호
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    • pp.172-177
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    • 2010
  • 중수로원전에서 환경으로 배출되는 방사성유출물의 양은 경수로원전에 비해 상대적으로 많고, 방사성유출물을 계속적으로 배출하는 연속배출(Continuous release) 방식으로 운용되고 있다. 이 때문에 원자로건물 배기 굴뚝(Stack) 등 주요 배출지점에 방사선검출기(Radiation detector)를 설치하여 방사성유출물의 농도를 실시간으로 감시하고 있다. 또한 방사성핵종 별로 연간 배출 가능한 유도배출한계(Derived Release Limits: DRLs)를 정하고, 이들 설정 값을 초과하지 않도록 엄격하게 관리하고 있다. 본 논문은 중수로원전 방사성유출물에 대한 배출관리 방식, 유도배출한계의 설정기준, 설정 방법론과 설정 현황을 조사하여 검토하였다.

복사열손실이 있는 비예혼합 튜브형 화염에 관한 수치 해석적 연구 (A Numerical Study of Opposed Nonpremixed Tubular Flames with Radiative Heat Loss)

  • 박현수;유춘상
    • 한국연소학회:학술대회논문집
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    • 한국연소학회 2015년도 제51회 KOSCO SYMPOSIUM 초록집
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    • pp.247-250
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    • 2015
  • The characteristics of opposed nonpremixed tubular flames with radiation heat loss are investigated using linear stability analysis and 2-D numerical simulations. Two extinction limits, as the $Damk{\ddot{o}}hler$ number is small or large, are confirmed using finite difference method with a simple continuation method. It is verified that the results of linear stability analysis predict the number of flame cells and the critical Da starting cellular instability or amplification of temperature near both extinction limits with good resolution.

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선량환산인자를 이용한 기체유출물 RMS 경보설정 개선방안 (Alarm Setpoint Determination Method of Gaseous Effluent Radiation Monitoring Systems Using Dose Factors Based on ICRP-60 Recommendations)

  • 박규준;김희근;하각현;엄희문
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2003년도 가을 학술논문집
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    • pp.491-496
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    • 2003
  • ICRP-60의 방사선방호 신개념이 국내 법령에 도입됨에 따라 원전 방사성유출물 관리의 변경이 불가피한 실정이다. 방사성유출물 관리의 중요한 요소 중의 하나가 원전 방사선감시계통(Radiation Monitoring System)의 적절한 운용이다. RMS는 원자력법에 명시되어 있는 일반인의 선량한도와 배출관리기준을 만족하도록 운용되어야 한다. 방사성유출물을 제한하는 기준에 따른 RMS 경보설정치의 비교ㆍ분석을 통해 국내 원전에 적용 가능한 최적의 개선방안을 제시할 수 있다. 본 논문에선 선량한도 기준 중 가능한 모든 피폭경로를 고려하여 예상선량률을 계산한 선행 RMS 경보설정 개선방안과의 비교를 위해 주요 피폭경로만 고려하는 선량환산인자에 의한 예상선량률 계산과 RMS 경보설정 개선방안을 조사하였다.

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Environment Assessing for Airborne Radioactive Particulate Release-introduction of Methods in IAEA Safety Report Series No.19

  • Meng, Dan;Yang, Liu;Shen, Fu;Yang, Yi;Ma, Yinghao;Ma, Tao;Zhang, Zhilong;Fu, Cuiming
    • Journal of Radiation Protection and Research
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    • 제41권4호
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    • pp.409-417
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    • 2016
  • Background: Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. Materials and Methods: This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). Results and Discussion: The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. Conclusion: It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment.

Airborne HPGe spectrometer for monitoring of air dose rates and surface activities

  • Marcel Ohera;Lubomir Gryc;Irena Cespirova;Jan Helebrant;Lukas Skala
    • Nuclear Engineering and Technology
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    • 제55권11호
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    • pp.4039-4047
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    • 2023
  • This contribution describes the application of HPGe detector for the airborne quantitative analysis. The hardware of the airborne HPGe system was designed from the commercial components with only exception of the newly designed AirHPGeSpec special software to control, measure and process the data. The system was calibrated for the local air kerma rates measured on helicopter board and its conversion to the air kerma rates at 1 m above the ground was proposed. Two examples of the air kerma rates measured over the former uranium mining areas are presented and compared with the results of other airborne system on the board. This airborne HPGe system could be also used for measuring the surface activities in a radiation event. The nuclides of 131I, 132Te - 132I, 133I, 134I, 135I, 137Cs, 134Cs, 88Rb and 103Ru were selected from possible nuclear power plant emergency scenarios. The Monte Carlo simulation was used to calculate HPGe detector efficiencies for the flight altitudes from 25 to 300 m for the energies from 300 keV to 3 MeV of the nuclides in question. Also, the detection limits according to the Currie method as well as ISO 11929-2010 for selected nuclides are presented.

CANDU형 원전에서의 유도방출한도 결정 (Determination of Derived Release Limits for a CANDU Nuclear Power Plant)

  • 김교윤;황해룡;김종경
    • Journal of Radiation Protection and Research
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    • 제19권1호
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    • pp.23-35
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    • 1994
  • CANDU형 원자력 발전소에서의 유도방출한도를 계산하기 위한 전산 코드 DRL이 개발되었다. DRL 코드에서의 유도방출한도는 CANDU형 원자력 발전소가 정상 가동될 때의 기체 및 액체 방출물에 포함된 방사성 핵종의 방출 허용 기준을 설정하기 위한 것이다. 본 전산 코드는 CSA Standard N288.1-M87에서 권고하고 있는 방법 및 다수 매개 변수를 이용하였고, 월성 원자력 발전소를 대상으로 유도방출한도를 결정하는데 이용되었다.

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Radioactive effluents released from Korean nuclear power plants and the resulting radiation doses to members of the public

  • Kong, Tae Young;Kim, Siyoung;Lee, Youngju;Son, Jung Kwon;Maeng, Sung Jun
    • Nuclear Engineering and Technology
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    • 제49권8호
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    • pp.1772-1777
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    • 2017
  • Korean nuclear power plants (NPPs) periodically evaluate the radioactive gaseous and liquid effluents released from power reactors to protect the public from radiation exposure. This paper provides a comprehensive overview of the release of radioactive effluents from Korean NPPs and the effects on the annual radiation doses to the public. The amounts of radioactive effluents released to the environment and the resulting radiation doses to members of the public living around NPPs were analyzed for the years 2011-2015 using the Korea Hydro & Nuclear Power Co., Ltd's annual summary reports of the assessment of radiological impact on the environment. The results show that tritium was the primary contributor to the activity in both gaseous and liquid effluents. The averages of effective doses to the public were approximately on the order of $10^{-3}mSv$ or $10^{-2}mSv$. Therefore, even though Korean NPPs discharged some radioactive materials into the environment, all effluents were within the regulatory safety limits and the resulting doses were much less than the dose limits.

Molecular Weight Control of Chitosan Using Gamma Ray and Electron Beam Irradiation

  • Kim, Hyun Bin;Lee, Young Joo;Oh, Seung Hwan;Kang, Phil Hyun;Jeun, Joon Pyo
    • 방사선산업학회지
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    • 제7권1호
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    • pp.51-54
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    • 2013
  • Chitosan is a useful natural polymer material in many application fields such as biomaterials, water-treatment, agriculture, medication, and food science. However, the poor solubility limits its application. In this study, the effects of radiation on chitosan were investigated using gamma ray and electron beam irradiation. The chemical structure and molecular weight analysis show similar degradation effects of chitosan powder in both gamma ray and electron beam irradiation. However, the radiation irradiated chitosan in $H_2O$ has a lower molecular weight, since the hydroxyl radicals attack the glycosidic bonds. This effect is more clearly shown in the electron beam irradiation results.