• 제목/요약/키워드: Radioactive Source

검색결과 292건 처리시간 0.024초

방사능오염 스크랩(scrap) 감지장치 개발 (The radiation monitoring system against radioactive material in SCRAP)

  • 이진우;김기홍
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
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    • pp.8-10
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    • 1997
  • In recent years, the metal industry has become increasingly aware of an unwanted component in metal scrap-radioactive material. Worldwide, there have 38 instances where radioactive sources were unintentionally smelted in the course of recycling metal scrap. In some cases contaminated metal consumer products were distributed internationally. U.S. mill that have smelted a radioactive source face costs resulting from decontamination, waste disposal, and lost profits that range from 7 to 23 million U.S. dollars for each case. Despite radiation monitoring system does not provide 100% protection, POSCO has developed the system for the first time in the steel industry of KOREA.

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Evaluation of Radioactive Source Terms in the System-Integrated Modular Advanced Reactor

  • Kim, Seong-Uck;Kang, Chang-Sun
    • Nuclear Engineering and Technology
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    • 제31권1호
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    • pp.9-16
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    • 1999
  • A 330 MWt-sized multi-purpose integral-type reactor, SMART is under development in Korea for the use of nuclear energy other than electricity generation. In this study, various radioactive source terms are estimated for SMART. SMART is different from conventional reactor concepts in operation and design. Therefore Specific Calculation method namely recurrence model is used. This model is based on the change rate in the RC radioactivity materials and operational characteristics of SMART Calculation results show tremendously increase of the levels of RC activity because no cleanup of RC and long term operation.

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Calculation of Detector Positions for a Source Localizing Radiation Portal Monitor System Using a Modified Iterative Genetic Algorithm

  • Jeon, Byoungil;Kim, Jongyul;Lim, Kiseo;Choi, Younghyun;Moon, Myungkook
    • Journal of Radiation Protection and Research
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    • 제42권4호
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    • pp.212-221
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    • 2017
  • Background: This study aims to calculate detector positions as a design of a radioactive source localizing radiation portal monitor (RPM) system using an improved genetic algorithm. Materials and Methods: To calculate of detector positions for a source localizing RPM system optimization problem is defined. To solve the problem, a modified iterative genetic algorithm (MIGA) is developed. In general, a genetic algorithm (GA) finds a globally optimal solution with a high probability, but it is not perfect at all times. To increase the probability to find globally optimal solution rather, a MIGA is designed by supplementing the iteration, competition, and verification with GA. For an optimization problem that is defined to find detector positions that maximizes differences of detector signals, a localization method is derived by modifying the inverse radiation transport model, and realistic parameter information is suggested. Results and Discussion: To compare the MIGA and GA, both algorithms are implemented in a MATLAB environment. The performance of the GA and MIGA and that of the procedures supplemented in the MIGA are analyzed by computer simulations. The results show that the iteration, competition, and verification procedures help to search for globally optimal solutions. Further, the MIGA is more robust against falling into local minima and finds a more reliably optimal result than the GA. Conclusion: The positions of the detectors on an RPM for radioactive source localization are optimized using the MIGA. To increase the contrast of the measurements from each detector, a relationship between the source and the detectors is derived by modifying the inverse transport model. Realistic parameters are utilized for accurate simulations. Furthermore, the MIGA is developed to achieve a reliable solution. By utilizing results of this study, an RPM for radioactive source localization has been designed and will be fabricated soon.

비파괴검사 분야에서 방사선원의 위치 확인을 위한 산화납 기반 방사선 검출기 설계에 관한 연구 (The Study on Design of lead monoxide based radiation detector for Checking the Position of a Radioactive Source in an NDT)

  • 안기정
    • 한국방사선학회논문지
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    • 제11권4호
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    • pp.183-188
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    • 2017
  • 최근, 감마선 조사기의 자동 원격 조사 제어기가 오동작하여 방사선작업종사자가 방사선 피폭 사고가 지속적으로 보고되고 있다. 이에 NDT 분야에서는 방사선에 대한 잠재적 사고를 미연에 방지하기 위한 방사선원 모니터링 시스템 구축에 많은 시간과 재원을 투자하고 있다. 이에 본 연구에서는 다양한 비파괴검사장비에 범용적으로 적용할 수 있는 방사선원 위치 모니터링 시스템의 개발을 위한 선행연구로써 몬테카를로 시뮬레이션을 통해 산화납 기반 방사선 검출기에 대한 감마선 응답 특성을 모의 추정하였다. 연구 결과, 방사선 검출기의 최적화 두께는 방사선원에서 방사되는 감마선 에너지에 따라 상이하며 에너지가 증가함에 따라 최적화 두께가 점차 증가하는 것으로 나타났다. 결론적으로 PbO 기반 방사선 검출기의 최적화 두께는 Ir-192에 대하여 $200{\mu}m$, Se-75 $150{\mu}m$, Co-60 $300{\mu}m$로 분석되었다. 이러한 연구 결과를 바탕으로 범용적으로 적용하기 위하여 2차 전자 평형을 고려한 PbO 기반 방사선 검출기의 적절한 두께는 $300{\mu}m$로 평가되었다. 이러한 결과는 차후 다양한 NDT 장비에 범용적으로 적용하기 위한 방사선원 위치 모니터링 시스템을 개발 시 방사선 검출기에서 요구되는 적절한 두께를 결정하는데 있어 기초자료로 활용될 수 있을 것으로 사료된다.

A Study of Simple α Source Preparation Using a Micro-coprecipitation Method

  • Lee, Myung Ho;Park, Tae-Hong;Song, Byung Chul;Park, Jong Ho;Song, Kyuseok
    • Bulletin of the Korean Chemical Society
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    • 제33권11호
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    • pp.3745-3748
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    • 2012
  • This study presents a rapid and simple ${\alpha}$ source preparation method for a radioactive waste sample. The recovery of $^{239}Pu$, $^{232}U$ and $^{243}Am$ using a micro-coprecipitation method was over 95%. The ${\alpha}$-peak resolution of Pu and Am isotopes through the micro-coprecipitation method is enough to discriminate the Pu and Am isotopes from other Pu and Am isotopes. The determination of the Pu and Am isotopes using the micro-coprecipitation method was applied to the radioactive waste sample, so that the activity concentrations of the Pu and Am isotopes using the micro-coprecipitation method in the radioactive waste sample were similar to those using the electrodeposition method.