• 제목/요약/키워드: dose assessment

검색결과 945건 처리시간 0.027초

Development of Internal Dose Assessment Procedure for Workers in Industries Using Raw Materials Containing Naturally Occurring Radioactive Materials

  • Choi, Cheol Kyu;Kim, Yong Geon;Ji, Seung Woo;Koo, Boncheol;Chang, Byung Uck;Kim, Kwang Pyo
    • Journal of Radiation Protection and Research
    • /
    • 제41권3호
    • /
    • pp.291-300
    • /
    • 2016
  • Background: It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. Materials and Methods: The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. Results and Discussion: The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are $10Bq{\cdot}g^{-1}$ for $^{40}K$ and $1Bq{\cdot}g^{-1}$ for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups ( < 0.1 mSv, 0.1-0.3 mSv, and > 0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels ( < 0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and > 1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. Conclusion: The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries.

Multi-layers grid environment modeling for nuclear facilities: A virtual simulation-based exploration of dose assessment and dose optimization

  • Jia, Ming;Li, Mengkun;Mao, Ting;Yang, Ming
    • Nuclear Engineering and Technology
    • /
    • 제52권5호
    • /
    • pp.956-963
    • /
    • 2020
  • Dose optimization for Radioactive Occupational Personal (ROP) is an important subject in nuclear and radiation safety field. The geometric environment of a nuclear facility is complex and the work area is radioactive, so traditional navigation model and radioactive data field cannot form an effective environment model for dose assessment and dose optimization. The environment model directly affects dose assessment and indirectly affects dose optimization, this is an urgent problem needed to be solved. Therefore, this paper focuses on an environment model used for Dose Assessment and Dose Optimization (DA&DO). We designed a multi-layer radiation field coupling modeling method, and then explored the influence of the environment model to DA&DO by virtual simulation. Then, a simulation test is done, the multi-layer radiation field coupling model for nuclear facilities is demonstrated to be effective for dose assessment and dose optimization through the experiments and analysis.

다양한 위해성평가 방법에 따라 도출한 토양오염 판정기준의 차이에 관한 연구(III): 우리나라 납 오염 위해성평가 방법 제안 (Analysis on the Risk-Based Screening Levels Determined by Various Risk Assessment Tools (III): Proposed Methodology for Lead Risk Assessment in Korea)

  • 정재웅;남경필
    • 한국지하수토양환경학회지:지하수토양환경
    • /
    • 제20권6호
    • /
    • pp.1-7
    • /
    • 2015
  • The most critical health effect of lead exposure is the neurodevelopmental effect to children caused by the increased blood lead level. Therefore, the endpoint of the risk assessment for lead-contaminated sites should be set at the blood lead level of children. In foreign countries, the risk assessment for lead-contaminated sites is conducted by estimating the increased blood lead level of children via oral intake and/or inhalation (United States Environmental Protection Agency, USEPA), or by comparing the estimated oral dose to the threshold oral dose of lead, which is derived from the permissible blood lead level of children (Dutch National Institute for Public Health and the Environment, RIVM). For the risk assessment, USEPA employs Integrated-Exposure-Uptake-Biokinetic (IEUBK) Model to check whether the estimated portion of children whose blood lead level exceeds 10 µg/dL, threshold blood lead level determined by USEPA, is higher than 5%, while Dutch RIVM compares the estimated oral dose of lead to the threshold oral dose (2.8 µg/kg-day), which is derived from the permissible blood lead level of children. In Korea, like The Netherlands, risk assessment for lead-contaminated sites is conducted by comparing the estimated oral dose to the threshold oral dose; however, because the threshold oral dose listed in Korean risk assessment guidance is an unidentified value, it is recommended to revise the existing threshold oral dose described in Korean risk assessment guidance. And, if significant lead exposure via inhalation is suspected, it is useful to employ IEUBK Model to derive the risk posed via multimedia exposure (i.e., both oral ingestion and inhalation).

화학물질의 건강 위해성 평가를 위한 수학 통계적 추계 모델링의 응용 (Application of Mathematical Modeling to Extraplate from High Dose to Low Dose for Risk Assessment of Vinyl Chloride)

  • 이영조;이석호;이승진;정진호
    • 한국식품위생안전성학회지
    • /
    • 제15권3호
    • /
    • pp.267-270
    • /
    • 2000
  • 본 연구에서는 유해한 화학물질인 vinyl chloride에 대한 건강 위해성 평가의 주요한 단계인 용량-반응 평가(dose-response assessment)를 수행함에 있어서 실험동물을 대상으로 한 발암성 자료를 사용하여 인체 위해도(risk)를 예측하고자 하였다. 용량 반응 평가에서는 고농도의 독성 자료로 부터 인체에 노출되는 수준인 저농도로 외삽을 위하여 computer software를 사용하지 않고 직접 다양한 통계 모델링을 사용하여 위해도를 산출하였다 이는 추후 국내 화학물질의 위해도 평가시 광범위하게 활용될수 있는 기초자료를 제공할 것이다.

  • PDF

Risk Assessment for Noncarcinogenic Chemical Effects

  • Kodell Ralph L.
    • 대한예방의학회:학술대회논문집
    • /
    • 대한예방의학회 1994년도 교수 연수회(환경)
    • /
    • pp.412-415
    • /
    • 1994
  • The fundamental assumption that thresholds exist for noncarcinogenic toxic effects of chemicals is reviewed; this assumption forms the basis for the no-observed-effect level/ safety-factor (NOEL/SF) approach to risk assessment for such effects. The origin and evolution of the NOEL/SF approach are traced, and its limitations are discussed. The recently proposed use of dose-response modeling to estimate a benchmark dose as a replacement for the NOEL is explained. The possibility of expanding dose-response modeling of non carcinogenic effects to include the estimation of assumed thresholds is discussed. A new method for conversion of quantitative toxic responses to a probability scale for risk assessment via dose-response modeling is outlined.

  • PDF

Derivation of a new dose constraint applicable to radioactive discharges from Korean nuclear power plants through retrospective dose assessment

  • Kim, Soyun;Cheong, Jae Hak
    • Nuclear Engineering and Technology
    • /
    • 제54권10호
    • /
    • pp.3660-3671
    • /
    • 2022
  • A new methodology to derive a dose constraint for radioactive effluent from a unit of nuclear power plant (NPP) through retrospective assessment was developed to reflect operational flexibility in line with international standards. The new dose constraint can retain the safety margin between the offsite dose and the past dose constraints. As case studies, the new approach was applied to 24 Korean NPPs to address the limitations of the existing seven dose constraints that do not fully comply with current international radiation protection standards. Therefore, an effective dose constraint for Korean NPPs was proposed as no less than 0.15 mSv/y, which is comparable to the international practices and previous studies (0.05-0.3 mSv/y). Although the lower bound of the equivalent dose constraint was calculated as 0.17 mSv/y, it is not proposed in this study since the compliance with the derived effective dose constraint can prevent accompanied equivalent doses to any organs from exceeding equivalent dose limits. The new framework and the case studies are expected to contribute toward and support the revision of existing dose constraints for radioactive effluent from NPPs, ensuring better compliance with the current international safety standards as well as reflect the operational flexibility in practice.

고준위폐기물 처분장 안전성평가 관련 타 국가의 기술기준 (Technical Standards on the Safety Assessment of a HLW Repository in Other Countries)

  • 이성호;황용수
    • 방사성폐기물학회지
    • /
    • 제7권3호
    • /
    • pp.183-190
    • /
    • 2009
  • 고준위폐기물 처분장의 기본적인 기능은 단기간에 과도한 방사성핵종이 유출되는 것을 방지하는데 있다. 이를 위해서는, 처분시스템의 구성요소들과 관련된 많은 기술 기준이 개발되고 수립되어야 한다. 처분장 안전성평가는 합리적으로 단순화된 모델에 바탕을 두고 처분장의 미래 전개에 대한 정량적인 결과를 산출하므로 안전성평가는 기술기준의 하나로 간주되고 있다. 본문에서는 평가기간, 선량 제한치 및 평가의 불확실성 등을 중심으로 안전성평가와 관련된 주요국의 기술기준을 조사하였다. 특히, 미국의 기준을 조사하는 과정에서 안전성평가에서 도출된 peak dose가 선량 제한치를 충족하지 못하는 경우, 평가기간 및 peak dose에 대한 미국 규제당국의 접근방안은 참고할만한 가치가 있음을 알 수 있었다.

  • PDF

The System of Radiation Dose Assessment and Dose Conversion Coefficients in the ICRP and FGR

  • Kim, Sora;Min, Byung-Il;Park, Kihyun;Yang, Byung-Mo;Suh, Kyung-Suk
    • Journal of Radiation Protection and Research
    • /
    • 제41권4호
    • /
    • pp.424-435
    • /
    • 2016
  • Background: The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. Materials and Methods: The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. Results and Discussion: A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. Conclusion: The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.

위해성 평가 및 관리에 있어서 발암물질의 인체발암능력 평가 (Estimation of Human Carcinogenic Potency (HCP) of Carcinogens in Risk Assessment and Management.)

  • 이병무;김대영;김세기;김근종
    • 한국환경성돌연변이발암원학회지
    • /
    • 제19권1호
    • /
    • pp.39-45
    • /
    • 1999
  • Human Carcinogenic Potency (HCP) can be estimated based on human daily exposure dose to carcinogen (Dh), body weight (Wh), 10% tumorigenic dose (TD10), and slope factor at TD10 (Q10) from 2-yr bioassay data. This approach is more relevant to humans generally exposed to low doses of carcinogens and can reduce more of extrapolation errors from high dose in animal experiments to low dose in humans than HERP (human exposure dose/rodent potency dose) proposed by Ames et al. (Science, 236, 271-280, 1987). TD50 and HERP have been routinely used to compare rodent carcinogenic potency and human carcinogenic potency, but those approaches have had limitations in extrapolation of high dose to low dose in humans. The advantages of HCP are to estimate human exposure dose (Dh) by human monitoring instead of environmental monitoring, to consider slope factor (Q10) which reflects the tendency of curve at low dose, and to use TD10 which represents much lower dose thant TD50 or HERP. HCP will be a useful parameter for the estimation of human carcinogenic potency in risk assessment and management of carcinogens.

External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, Korea

  • Lee, ChoongWie;Lee, Donghyun;Kim, Hee Reyoung;Lee, Seung Jun
    • Nuclear Engineering and Technology
    • /
    • 제52권9호
    • /
    • pp.2085-2091
    • /
    • 2020
  • The license for Kori-1, the first commercial reactor in Busan, Korea, was terminated in June 2017; therefore, preparations are being made for its decommissioning. Because the radioactivity of Bio-shield varies greatly throughout the structure, the doses received by the workers depend on the location, order, and duration of dismantling operations. Thus, a model for evaluating the worker external dose during the dismantling of the Kori-1 bio-shield was developed, and work scenarios for dose assessment were designed. The Dose evaluation code VISIPLAN was used for dose assessment. The dose rate around the bio-shield was evaluated and the level of exposure to the operator was evaluated according to the work scenario. The maximum annual external dose was calculated as 746.86 mSv for a diamond wire saw operator under dry cutting conditions, indicating that appropriate protective measures, such as changing dismantling sequence, remote monitoring, shield installation, and adjustment of work team are necessary for the safe dismantling of the bio-shield. Through these protective measures, it was found that the worker's dose could be below the dose limit.