• 제목/요약/키워드: Nuclear facilities

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원전 생애주기간 설계기준 정보관리를 위한 요건 분류체계 개발 (Development of Requirement Taxonomy for Design Bases Management during NPP lifecycle)

  • 김종명
    • 한국건축시공학회:학술대회논문집
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    • 한국건축시공학회 2018년도 추계 학술논문 발표대회
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    • pp.134-135
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    • 2018
  • Nuclear Power Plant consists of about 1.4 million facilities. and the design standards and design requirements for the continuos utilization and safety of facilities are complexly connected with the facilities. When a design change for facilities or design requirements is occurred at the time of construction or operation, there are a lot of facilities, design requirements, and design bases that are affected by the facilities or design bases being changed. The above design changes are so complex that the existing document-bases design change process is time-consuming and may also cause human error. In this study, we developed a design requirement taxonomy that can be applied to the data-centric design bases document that can improve it. To do this, we analyze the design elements from the highest level to the lowest level applied to the nuclear power plant, and classify the design elements according to the characteristics of the design elements.

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Study on the characteristics of airborne gross alpha and gross beta activities in the vicinity of nuclear facilities

  • Da-Young Gam;Chae-yeon Lee;Ji-Young Park;Hyuncheol Kim;Jong-Myoung Lim
    • Nuclear Engineering and Technology
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    • 제55권12호
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    • pp.4554-4560
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    • 2023
  • Continuous monitoring of radioactive substances over a prolonged duration can yield crucial insights into the levels of radiation exposure through inhalation, both in the vicinity of nuclear facilities and/or general environments. In this study, we evaluated long-term measurements (2012-2022) of gross alpha-beta activities in the air in the vicinity of nuclear facilities and reference site, distribution characteristics of temporal trends and spatial fluctuations, and factors affecting radioactivity levels. The average airborne gross-α (in mBq m-3) for onsite and off-site were 0.124 and 0.117, respectively, and the average airborne gross-β (in mBq m-3) measurements were 1.10 and 1.04, respectively. The activity ratio (AR) of gross-α and gross-β were calculated as a ratio of 0.12. The distribution characteristics of gross-α and gross-β activities in this study area are likely influenced by the meteorological factors and variations in airborne PM concentrations rather than the operation of the nuclear facility.

원자력시설의 필수디지털자산에 대한 기술적 보안조치항목에 대한 연구 (A Study on the Implementation of Technical Security Control for Critical Digital Asset of Nuclear Facilities)

  • 최윤혁;이상진
    • 정보보호학회논문지
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    • 제29권4호
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    • pp.877-884
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    • 2019
  • 기술발전에 따라 원자력시설에 사용되는 장비가 아날로그 시스템에서 디지털 시스템으로 변경되는 추세이다. 컴퓨터와 디지털시스템의 비율이 증가함에 따라 원자력시설은 사이버 위협에 노출되었다. 그 결과 사이버보안에 대한 관심이 높아지고 사이버 공격으로부터 시스템을 보호해야 한다는 인식의 변화가 생겼다. 국내 규제기관에서 발행한 KINAC/RS-015는 필수디지털자산에 대해 101가지 사이버보안 통제항목을 제시하였지만 디지털자산의 특성을 고려하지 않은 일반적인 항목이다. 모든 사이버보안 통제항목을 필수디지털자산에 적용하는 것은 많은 작업량과 효율성을 떨어뜨린다. 본 논문에서는 필수디지털자산의 특성을 파악하고 적절한 보안조치항목을 제시함으로써 효과적인 사이버 보안 통제항목 적용을 제안한다.

Bed-type과 Stand-type 상용 전신계수기(Whole Body Counter)의 성능 비교 (Performance Comparison of Bed-type and Stand-type Commercial Whole Body Counter Made by Canberra for Internal Exposure Monitoring)

  • 김봉기;하위호;권태은;박민석;이준호;김종민;이상경;정규환
    • 대한방사선기술학회지:방사선기술과학
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    • 제41권5호
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    • pp.437-444
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    • 2018
  • Whole-Body counters have been used to evaluate the internal contamination of gamma emitting radionuclides. Among the whole-body counters used in domestic nuclear facilities, Fastscan made by CANBERRA contains 2 NaI(Tl) detectors and is generally used to monitor the primary internal exposure. It has the advantage of achieving MDA even with short time measurements. Accuscan is a bed type, and has good energy resolution because it is composed of HPGe detector. Since the Accuscan with better energy resolution than Fastscan has better able to identify radionuclides, it is used to monitor secondary internal exposure. Some nuclear facilities have only Fastscan. We analyzed statistically whether Fastscan is enough to ensure accuracy and precision comparing with Accuscan. To do this, we prepared a CRM created by the Korea Research Institute of Standards and Science. We also obtained the data of 6 Fastscans and 5 Accuscans in domestic nuclear facilities. As a result of the study, although Fastscan compared with Accuscan is not as accurate as the Accuscan, the precision is statistically same. However, accuracy of Fastscan is in compliance with international standards except low energy range. In terms of accuracy and precision except radionuclides emitting low energy, it is possible to measure radioactivity inside workers even in nuclear facilities where only Fastscan is used.

Radiological Dose Assessment Due to the Operation of Nuclear Facilities at KAERI Nuclear Site

  • Han, M.H.;Kim, E.H.;Hwang, W.T;Yeom, J.M.;Han, J.T.;Lee, Y.B.;Han, W.J.
    • Journal of Radiation Protection and Research
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    • 제28권3호
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    • pp.247-254
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    • 2003
  • To prevent the potential health detriment to the public from radioactive effluents, radiological dose assessments due to the operation of nuclear facilities located at Korea Atomic Energy Research Institute (KAERI) site has been performed semiannually in compliance with the Minister of Science and Technology (MOST)'s Notice in Korea. Radiological dose assessment based on the new recommendation of the International Committee on Radiation Protection (ICRP-60) has been conducted since 1998. In this manuscript, a serial activities at KAERI site to meet the regulatory standards for routine releases of radioactive effluents are introduced and discussed including technical approaches. It is clear that each nuclear facility has been operated in compliance with regulatory standards. Furthermore, it is identified that the radiation induced health effects for residents around the site are neglectable.

Online training and education from the VR-1 reactor-Lessons learned

  • Ondrej Novak;Tomas Bily;Ondrej Huml;Lubomir Sklenka;Filip Fejt;Jan Rataj
    • Nuclear Engineering and Technology
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    • 제55권12호
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    • pp.4465-4471
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    • 2023
  • Hands-on education and training is a key part of fixing and developing technology knowledge and is an inherent part of many engineering and scientific curricula. However, access to large complex training facilities, such as nuclear reactor, could be limited by various factors, such as unavailability of those facilities in the region, high traveling costs or harmonization of the schedules of hands-on E&T with theoretical lectures and with the operational schedule of the facility. To handle the issue, several success stories have been reached with the introduction of the Internet Reactor Labs (IRL). The Internet Reactor Labs can strongly contribute to accessibility of training at research reactors and can contribute to improvements in their utilization. The paper describes the development of the Internet Reactor Lab at the VR-1 reactor of the Czech Technical University in Prague. Contrary to single-purpose IRLs, it presents various modalities of online teaching and training in experimental reactor physics and reactor operation in general as well as outreach activities that have been developed in recent years.