• 제목/요약/키워드: Domestic regulations on radiation safety

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방사선안전규제 측정도구 개발 (Development of a Measurement Tool for Radiation Safety Regulations)

  • 한은옥
    • 한국산학기술학회논문지
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    • 제13권12호
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    • pp.6203-6207
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    • 2012
  • 방사선이용 기관의 증가에 따라 방사선안전규제의 수요도 지속적으로 증가하고 있으므로 방사선안전규제의 합리화를 위한 객관적인 근거자료를 도출하기 위해서 방사선안전관리자를 통한 실질적인 일반화된 측정도구를 개발하고자 하였다. US NRC NUREG 1556(방사성물질에 대한 통합지침) Vol 1~21의 내용, 원자력안전법 등의 내용을 근거로 예비문항을 작성하여 국내 방사선이용 허가기관의 약 10%에 해당되는 방사선안전관리자를 대상으로 설문조사를 실시하였다. 그 결과, 요인분석 20개 문항에 대해 3개의 요인이 추출되었다. 요인1은 '방사선안전관리 규제요건', 요인2는 '실질적인 안전규제의 부합성', 요인3은 '방사선원 분류'관련으로 각각 명명하였다. 각 요인의 분산 설명력은 요인1이 40.140%, 요인2가 13.721%, 요인3이 6.556%로서 전체 60.417%의 설명력을 나타내었다. 본 연구에서 도출된 방사선안전규제 측정도구를 사용하여 방사선안전규제 기준을 도출한다면 국제기준에 적합할 뿐만 아니라 현장의 방사선안전관리자에게 실용성 있는 기준을 제시할 수 있을 것이라고 사료된다.

방사선안전규제 요건별 인식도 차이 (Differences between Each Requirement for Radiation Safety Regulation Levels)

  • 한은옥;조대형
    • Journal of Radiation Protection and Research
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    • 제37권4호
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    • pp.219-225
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    • 2012
  • 방사선안전을 수행하는 방사선안전관리자를 대상으로 실제적인 방사선안전규제 수준을 파악하여 합리적인 안전규제 제도를 마련하는데 필요한 근거자료를 도출함으로써 방사선안전규제의 효율성과 편의성을 극대화할 수 있는 차별화된 규제에 도움이 되고자 하였다. IAEA의 RS-G-1.9 (2005), NRC의 NUREG Vol. 1~21 등과 국내 원자력안전법의 내용을 근거로 전체 약 10%에 해당되는 방사선이용기관의 방사선안전관리자를 대상으로 설문조사하였다. 피폭관리에 대한 요건($3.32{\pm}0.910$)이 가장 높은 인식수준을 나타냈고, 관련 서류의 기록, 비치, 보관에 대한 요건($2.84{\pm}0.826$)은 가장 낮은 인식수준을 나타냈다. 방사선원 현황 및 관리 요건, 시설 요건, 측정 및 오염관리 요건, 측정 장비 및 감시기 작동 요건, 교육 및 훈련 요건, 피폭관리 요건에서 산업기관이 의료기관보다 규제가 더 엄격해야 한다는 인식수준을 나타냈다. 방사선안전규제 수준이 산업기관과 의료기관에 통계적으로 유의한 차이가 있다는 것은 규제관련 그 원인이 존재하는 것이므로 실제적인 규제내용을 재평가해 볼 필요가 있음을 시사한다. 향후 연구에서는 국내 기관특성별로 규제요건을 개발하는 과정이 이루어질 필요가 있고, 기관특성을 고려하여 방사선안전규제를 수행한다면 편의성을 극대화한 안전규제를 달성할 수 있을 것이라고 사료된다.

Status of Domestic and International Recommendations for Protection Design and Evaluation of Medical Linear Accelerator Facilities

  • Choi, Sang Hyoun;Shin, Dong Oh;Shin, Jae-ik;Kwon, Na Hye;Ahn, So Hyun;Kim, Dong Wook
    • 한국의학물리학회지:의학물리
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    • 제32권4호
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    • pp.83-91
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    • 2021
  • Various types of high-precision radiotherapy, such as intensity-modulated radiation therapy (IMRT), tomotherapy (Tomo), and stereotactic body radiation therapy have been available since 1997. After being covered by insurance in 2015, the number of IMRT cases rapidly increased 18-fold from 2011 to 2018 in Korea. IMRT, which uses a high-beam irradiation monitor unit, requires higher shielding conditions than conventional radiation treatments. However, to date, research on the shielding of facilities using IMRT and the current understanding of its status are insufficient, and detailed safety regulation procedures have not been established. This study investigated the recommended criteria for the shielding evaluation of facilities using medical linear accelerators (LINACs), including 1) the current status of safety management regulations and systems in domestic and international facilities using medical LINACs and 2) the current status of the recommended standards for safety management in domestic and international facilities using medical LINACs. It is necessary to develop and introduce a safety management system for facilities using LINACs for clinical applications that is suitable for the domestic medical environment and corresponds to the safety management systems for LINACs used overseas.

국내·외 라돈 관련 제도 비교를 통한 산업안전보건법 개선방안 (Improvement of the Occupational Safety and Health Act by the Comparison of the Domestic and Foreign Radon-related Policies)

  • 임대성;김기연;조용민;서성철
    • 한국산업보건학회지
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    • 제31권3호
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    • pp.226-236
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    • 2021
  • Objectives: Concerns have been raised about the possible health effects of radon on both workers and consumers with the spread of social attention to the impact of radon exposure. Thus, an entire raw material handling workshop was investigated, and standards for radon levels in the workplace were newly established at 600 Bq/m3. However, regulations on the management of workers exposed to radon are still insufficiently developed. Therefore, by comparative analysis of overseas and domestic radon-related regulations for workplaces, this study aims to suggest improvement plans of protection regulations under the Occupational Safety and Health Act (OSH Act) for the prevention of health disorders of radon-exposed workers. Methods: For overseas case studies, we consulted radon-related laws and reports officially published on the websites of the European Union (EU), the United States (U.S.) and the United Kingdom (UK) government agencies. Domestic law studies were conducted mainly on the Act on Protective Action Guidelines against Radiation in the Natural Environment and the OSH Act. Results: In Europe, the basic safety standards for protection against risks arising from radon (Council Directive 2013/59/EURATOM of 5 December 2013) was established by the EU. They recommend that the Member States manage radon level in workplaces based on this criterion. In the U.S., the standards for workplaces are controlled by the Occupational Safety and Health Administration (OSHA) and the Mine Safety and Health Administration (MSHA). Action on radon in the UK is specified in "Radon in the workplace" published by the Health and Safety Executive (HSE). Conclusions: The Act on Protective Action Guidelines against Radiation in the Natural Environment mainly refers to the management of workplaces that use or handle raw materials but does not have any provisions in terms of protecting naturally exposed workers. In the OSH Act, it is necessary to define whether radon is included in radiation for that reason that its current regulations have limitations in ensuring the safety workers who may be exposed to naturally occurring radon. The management standards are needed for workplaces that do not directly deal with radon but are likely to be exposed to radon. We propose that this could be specified in the regulations for the prevention of health damage caused by radiation, not in Article 125 of the OSH Act.

GEANT4를 이용한 $^{99m}Tc$ Generator 안전성 시뮬레이션 ([ $^{99m}Tc$ ] Generator Safety Simulation Based on GEANT4)

  • 강상구;한동현;김종일
    • 한국의학물리학회지:의학물리
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    • 제19권1호
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    • pp.1-8
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    • 2008
  • 테크니슘$(^{99m}Tc)$은 현재 핵의학 분야에서 진단용 방사선원으로 가장 널리 쓰이고 있는 방사성 동위원소 중 하나이다. 일반적으로 테크니슘은 $^{99m}Tc$ Generator라 불리는 장치 안에서 모핵종인 $^{99}Mo$의 붕괴를 통해 생산되는데, $^{99}Mo$$^{99m}Tc$에서 비교적 높은 방사선을 방출하기 때문에 이를 차폐하기 위하여 주로 납으로 제작되어 있다. 본 논문에서는 국내에서 비교적 사용 빈도가 높고 교정 방사능이 500 mCi인 일본 제품을 대상으로, 최대 방사능량 적제조건에서 차폐용기 표면으로부터 10 cm, 100 cm에서 각각 2.0 mSv/h, 0.02 mSv/h를 초과하지 않아야 한다는 국내 법적 제한치를 만족시키는지 여부를 GEANT4를 이용하여 시뮬레이션하였다. 계산 결과 용기 밖으로 방출되는 방사선량이 법적 기준치를 초과하지 않는 것으로 나타났다.

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Re-evaluation of Korean Effluent Concentration Limits and Comparative Analysis

  • Hwang, Won Tae;Lee, Joeun;Kwon, Dahye;Kim, Eun Han;Han, Moon Hee
    • Journal of Radiation Protection and Research
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    • 제43권3호
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    • pp.124-129
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    • 2018
  • Background: Effluent Concentration Limits (ECLs) were re-evaluated via direct calculation using dose coefficients based on radiation protection quantity introduced in Korea and the intrinsic breathing rates of Korean residents. Materials and Methods: The re-evaluated ECLs were compared with the domestic standards given in the Notice of the Nuclear Safety and Security Commission (NSSC), as well as with ECLs specified in the Code of Federal Regulations (CFR). Results and Discussion: The relative ratios of the re-evaluated ECLs to the currently applied domestic standards differed depending on the radionuclide type, but it was clearly shown that, for tritium ($^3H$) and radiocarbon ($^{14}C$), which significantly affect radiological dose to the public during the normal operation of nuclear power plants, the re-evaluated ECLs were higher than the domestic standards. This implies that Korean standards are relatively conservative. Conclusion: The re-evaluated results for each age group showed that $^{131}I$ (radioiodine), one of the significant radionuclides, had the lowest values, but nonetheless, the domestic standards for radioiodine were lower than the ECLs given in the CFR and the re-evaluated ECLs via a method given in the CFR.

GEANT4를 이용한 치료용 I-131 캡슐의 안정성 시뮬레이션 (Safety Simulation of Therapeutic I-131 Capsule Using GEANT4)

  • 정영환;김병철;심철민;서한경;권용주;한동현
    • 핵의학기술
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    • 제18권2호
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    • pp.57-61
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    • 2014
  • 국내 갑상선암 환자의 발병률이 증가함에 따라 방사성요오드 치료가 필요한 환자가 증가하고 있다. 방사성 요오드 치료에 이용되고 있는 캡슐용기들 중 1.1 GBq과 5.5 GBq의 국산제품에 설계도면을 바탕으로 차폐체를 구현한 후 366 keV 이상에 감마선들에 대하여 캡슐용기의 방사선 누설선량을 GEANT4 전사모사를 이용하여 평가하였다. 치료용 I-131 캡슐용기 누설선량을 측정하기 위해 각각의 용기에 대하여 용기 표면에서 10 cm 거리 및 100 cm 거리에서의 누설선량을 측정하였다. 용기표면에서 10 cm 거리와 100 cm 거리에서의 누설선량 측정은 방사형으로 발생되는 방사선을 위치별로 측정하기 위해 $10{\times}10{\times}10cm^3$ 부피의 정육면체 형태의 물 팬텀(phantom)을 상부, 상부측면, 측면, 하부측면, 하부 다섯 방향에 설치하여 누설선량을 계산하였다. 용기별로 5개 방향에서 용기표면으로 부터 10 cm, 100 cm 거리에서 전산모사를 수행한 결과 법적 허용기준인 10 cm 거리에서 2.0 mSv/h, 100 cm 거리에서 0.02 mSv/h 이하의 선량 규정과 비교하였을 때 법적기준치보다 현저히 낮은 누설선량이 방출되는 것을 확인하였다.

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연안해역 전파환경의 분석과 운용개선 방안 (A Plain on Operation Improvement according to the Analysis of Radio Field's Environment in Domestic Coastal)

  • 윤재준;김병옥;최조천
    • 한국정보통신학회:학술대회논문집
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    • 한국해양정보통신학회 2005년도 춘계종합학술대회
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    • pp.1117-1124
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    • 2005
  • 주파수 대역에 따른 전파의 전파환경은 현저하게 다르므로 통신환경도 VHF대는 직접파에 의하며 HF대는 대부분 전리층 반사파에 의한다. 우리나라 연근해역의 비SOLAS 선박들의 해상통신은 선박안전법 시행규칙에 의하며 선박들은 지정된 무선설비를 탑재 하여 통신을 수행하게 된다. 본 논문에서는 VHF 및 HF 무선전화에 의하여 해상통신을 수행하는 연근해 선박들의 통신환경을 조사하고자 전파환경 시뮬레이션 프로그램을 활용하여 분석하였다. 그리고 연안 선박들의 현행 무선설비 탑재기준에 맞추어 분석된 자료를 근거로 전파환경과 통신현황을 예측하였으며, 관련규정을 합리적으로 개선시켜 나가는 방안과 VHF 해안국간의 네트워크 통합에 대한 필요성을 제시하였다.

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원자력시설 안전관리 법제의 문제점과 개선방안 연구 -수산물의 안전관리를 중심으로- (A Study on the Problems and Improvement of the Safety Management Law of Nuclear Facilities -Focused on Safety Management of Aquatic Products-)

  • 이우도
    • 수산경영론집
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    • 제50권2호
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    • pp.23-40
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    • 2019
  • The main purpose of this study is to analyze and examine the problems of the law systems of the safety and maintenance of nuclear facilities and to propose the improvements with respect to the related problems especialy focused on safety management of aquatic products. Therefore, the results of the paper would be helpful to build an effective management law system of safety and maintenance of nuclear facilities and fisheries products. The research methods are longitudinal and horizontal studies. This study compares domestic policies with foreign policies of nuclear plants and aquatic products. Using the above methods, examining the current system of nuclear-related laws and regulations, we have found that there exist 13 Acts including "Nuclear Safety Act", etc. Safety laws related on nuclear facilities have seven Acts including "Nuclear Safety Act", "the Act on Physical Protection and Radiological Emergency", "Radioactive waste control Act", "Act on Protective Action Guidelines against Radiation in the Natural Environment", "Special Act on Assistance to the locations of facilities for disposal low and intermediate level radioactive waste", "Korea Institute of Nuclear Safety Act". "Act on Establishment and Operation of the Nuclear Safety and Security Commission". The seven laws are composed of 119 legislations. They have 112 lower statute of eight Presidential Decrees, six Primeministrial Decrees and Ministrial Decrees, 92 administrative rules (orders), 6 legislations of local self-government aself-governing body. The concluded proposals of this paper are as follows. Firstly, we propose that the relationship between the special law and general law should be re-established. Secondly, the terms with respect to law system of safety and maintenance of nuclear plants should be redefined and specified. Thirdly, it is advisable to re-examine and re-establish the Law System for Safety and Maintenance of Nuclear Facilities. and environmental rights like the French Nuclear Safety Legislation. Lastly, inadequate legislation on the aquatic pollution damage should be re-established. It is necessary to ensure sufficient transparency as well as environmental considerations in the policy decisions of the Korean government and legislation of the National Assembly. It is necessary to further study the possibilities of accepting the implications of the French legal system as a legal system in Korea. In conclusion, the safety management of nuclear facilities is not only focused on the secondary industry and the tertiary industry centering on power generation and supply, but also on the primary industry, which is the food of the people. It is necessary to prevent damage to be foreseen. Therefore, it is judged that there should be no harm to the people caused by contaminated marine products even if the "Food Safety Law for Prevention of Radiation Pollution Damage" is enacted.

Radiological analysis of transport and storage container for very low-level liquid radioactive waste

  • Shin, Seung Hun;Choi, Woo Nyun;Yoon, Seungbin;Lee, Un Jang;Park, Hye Min;Park, Seong Hee;Kim, Youn Jun;Kim, Hee Reyoung
    • Nuclear Engineering and Technology
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    • 제53권12호
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    • pp.4137-4141
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    • 2021
  • As NPPs continue to operate, liquid waste continues to be generated, and containers are needed to store and transport them at low cost and high capacity. To transport and store liquid phase very low-level radioactive waste (VLLW), a container is designed by considering related regulations. The design was constructed based on the existing container design, which easily transports and stores liquid waste. The radiation shielding calculation was performed according to the composition change of barium sulfate (BaSO4) using the Monte Carlo N-Particle (MCNP) code. High-density polyethylene (HDPE) without mixing the additional BaSO4, represented the maximum dose of 1.03 mSv/hr (<2 mSv/hr) and 0.048 mSv/hr (<0.1 mSv/hr) at the surface of the inner container and at 2 m away from the surface, respectively, for a 10 Bq/g of 60Co source. It was confirmed that the dose from the inner container with the VLLW content satisfied the domestic dose standard both on the surface of the container and 2 m from the surface. Although it satisfies the dose standard without adding BaSO4, a shielding material, the inner container was designed with BaSO4 added to increase radiation safety.