• 제목/요약/키워드: dose assessment

검색결과 969건 처리시간 0.027초

전신방사선조사 시 선속 스포일러에 따른 선량 분포 및 영향 평가 (Beam Spoiler-dependent Total Body Irradiation Dose Assessment)

  • 이동연;김정훈
    • 대한방사선기술학회지:방사선기술과학
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    • 제41권2호
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    • pp.141-148
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    • 2018
  • This study examined the properties of photons and the dose distribution in a human body via a simulation where the total body irradiation(TBI) is performed on a pediatric anthropomorphic phantom and a child size water phantom. Based on this, we tried to find the optimal photon beam energy and material for beam spoiler. In this study, MCNPX (Ver. 2.5.0), a simulation program based on the Monte Carlo method, was used for the photon beam analysis and TBI simulation. Several different beam spoiler materials (plexiglass, copper, lead, aluminium) were used, and three different electron beam energies were used in the simulated accelerator to produce photon beams (6, 10, and 15 MeV). Moreover, both a water phantom for calculating the depth-dependent dosage and a pediatric anthropomorphic phantom for calculating the organ dosage were used. The homogeneity of photon beam was examined in different depths for the water phantom, which shows the 20%-40% difference for each material. Next, the org an doses on pediatric anthropomorphic phantom were examined, and the results showed that the average dose for each part of the body was skin 17.7 Gy, sexual gland 15.2 Gy, digestion 13.8 Gy, liver 11.8 Gy, kidney 9.2 Gy, lungs 6.2 Gy, and brain 4.6 Gy. Moreover, as for the organ doses according to materials, the highest dose was observed in lead while the lowest was observed in plexiglass. Plexiglass in current use is considered the most suitable material, and a 6 or 10 MV photon energy plan tailored to the patient condition is considered more suitable than a higher energy plan.

원자력시설 해체 작업자 보호 및 사고 예방을 위한 가상현실 기반의 훈련 시스템 (The training system based on virtual environments to protect workers and to prevent incidents and accidents during decommissioning of nuclear facilities)

  • 정관성;문제권;최병선;윤태만
    • 한국재난정보학회:학술대회논문집
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    • 한국재난정보학회 2015년 정기학술대회
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    • pp.294-297
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    • 2015
  • Decommissioning of nuclear facilities should be accomplished by assuring the safety of workers because decommissioning activities of nuclear facilities are under high radioactivity and work difficulty. It is necessary that before decommissioning, the radiation exposure dose of workers has to be evaluated and assessed under the principle of ALARA (as low as reasonably achievable). Furthermore, to improve the proficiency of decommissioning environments, method and system need to be developed. The legacy methods of exposure dose measurement and assessment had the limitations to modify and simulate the exposure dose to workers prior to practical activities because those should be accomplished without changes of working routes under predetermined scenarios. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. It can be concluded that this system is able to protect from accidents and enable workers to improve his familiarization about working environments. It is expected that this system can reduce human errors because workers are able to improve the proficiency of hazardous working environments due to virtual training like real decommissioning situations. In the end, the safety during decommissioning of nuclear facilities will be guaranteed under the principle of ALARA.

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Pentachlorophenol의 노출에 의한 사람 T-임파구의 hprt 유전자에서 돌연변이 빈도 (Mutant Frequency at the hprt Locus in Human T-Cell Exposed to Pentachlorophenol)

  • 윤병수;조명행;김인규;박선영;이영순
    • Toxicological Research
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    • 제13권1_2호
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    • pp.71-78
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    • 1997
  • The mutational effects of pentachlorophenol (PCP) on the hypoxanthine phosphoribosyl transf erase (hprt) locus in human T-cell were analysed by T-cell clonal assay in vitro. Cells were exposed for 24 hours at primary culture to 0~100 ppm (W/V) PCP in dimethyl sulfoxide. Treated cells were allowed at the same time to stimulate by phytohemagglutinin (PHA) and T-cell growth factor (TCGF) and then seeded in medium containing 6-thioguanine to select for hprt-negative routants. We have also defined the optimal condition for the determination of mutant frequency. The parameters investigated include survival counting, first and second subculture for clonal efficiency plating and mutant plating. Under the optimal conditions, mutant frequencies of high dose-treated cells were significantly higher than those of non-treated or low dose cells. The results indicated a clear dose-effect relationship and showed that mutant frequency in 50 ppm PCP treated cell was 4.31$\times$$10^{-5}$ (background, 8.32$\times$$10^{-6}$). Above data strongly suggest that hprt mutation assay can be used as a biomarker for the environmental risk assessment.

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나노도트선량계를 이용한 입사표면선량의 평가 (An Assessment of Entrance Surface Dose Using the nanoDot Dosimeter)

  • 김종언;임인철;박철우
    • 한국방사선학회논문지
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    • 제5권6호
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    • pp.377-381
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    • 2011
  • 이 연구의 목적은 일반방사선촬영에서 입사표면선량에 대하여 나노도트선량계의 측정값과 Non Dosimeter Dosimetry-Method(NDD-M)의 계산값과 비교 평가하는 데 있다. 입사표면선량들의 측정과 계산은 두부(AP), 복부(AP), 골반(AP), 흉추(AP)와 요추(AP)에 대하여 수행하였다. 결과로서, 계산값에 대한 측정값의 상대비들은 각 부위에 대하여 1.5-2.1을 얻었다. 재현성은 변동계수로서 0.035를 얻었다.

Transport Risk Assessment for On-Road/Sea Transport of Decommissioning Waste of Kori Unit 1

  • Woo Yong Kim;Hyun Woo Song;Jisoo Yoon;Moon Oh Kim
    • 방사성폐기물학회지
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    • 제21권2호
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    • pp.255-269
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    • 2023
  • Compared to operational wastes, nuclear power plant (NPP) decommissioning wastes are generated in larger quantities within a short time and include diverse types with a wider range of radiation characteristics. Currently used 200 L drums and IP-2 type transport containers are inefficient and restrictive in packaging and transporting decommissioning wastes. Therefore, new packaging and transport containers with greater size, loading weight, and shielding performance have been developed. When transporting radioactive materials, radiological safety should be assessed by reflecting parameters such as the type and quantity of the package, transport route, and transport environment. Thus far, safety evaluations of radioactive waste transport have mainly targeted operational wastes, that have less radioactivity and a smaller amount per transport than decommissioning wastes. Therefore, in this study, the possible radiation effects during the transport from NPP to disposal facilities were evaluated to reflect the characteristics of the newly developed containers and decommissioning wastes. According to the evaluation results, the exposure dose to transport workers, handling workers, and the public was lower than the domestic regulatory limit. In addition, all exposure dose results were confirmed, through sensitivity analysis, to satisfy the evaluation criteria even under circumstances when radioactive materials were released 100% from the container.

다중소자 열형광선량계에 의한 수정체 등가선량 평가의 적정성 연구 (A Feasibility Study on the Lens of Eye Dose Assessment Using the System of Multi-Element TLD)

  • 이나래;한승재;이병일;조건우
    • Journal of Radiation Protection and Research
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    • 제37권2호
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    • pp.96-102
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    • 2012
  • 2011년 국제방사선방호위원회(ICRP)는 최근 역학 조사들을 근거로 방사선영향으로 발생할 수 있는 암 외 질환의 위험에 대한 권고를 개정하였다. 특히 수정체 조직반응의 발단선량을 0.5 Gy로 하향 조정하면서, 계획 피폭상황에서 직무 피폭 시 수정체 등가선량한도를 "정해진 5년 기간 동안 평균해서 연간 20 mSv, 그 중 어느 한 해에도 50 mSv를 초과하지 않아야 한다"로 권고하였다. 방사선작업종사자의 외부선량은 개인 열형광선량계(TLD)를 사용하여 감시하고 있으며 판독한 열형광소자별 반응도를 선량평가 알고리즘에 적용하면 개인의 수정체 등가선량을 구할 수 있다. 본 논문에서는 성능검사에 사용된 Harshaw TLD의 소자반응도를 사용하여 현재 사용 중인 알고리즘들에 의한 수정체 등가선량을 평가하였다. 그 결과 성능검사에 사용된 TLD의 소자반응도를 사용하여 수정체 등가선량을 평가한 경우 알고리즘 간의 상대오차는 최대 48.84% 내에 있는 것으로 나타났다.

Karlsruhe 원자력연구소 주변의 환경방사능 측정자료로부터 실효선량당량계산 (A Calculation of Effective Dose Equivalent from Data of Environmental Monitoring around the Karlsruhe Nuclear Research Center)

  • 이창우;이정호
    • Journal of Radiation Protection and Research
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    • 제15권2호
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    • pp.75-85
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    • 1990
  • Kalsruhe원자력 연구소(KfK) 주변의 방사능 측정자료로부터 피폭선량을 계산하였다. 식물성 식품의 섭취가 가장 중요한 피폭 경로였고, 식품중의 자연방사성 동위원소인 K-40 과 Pb-210이 주요 피폭원이었다. 인공방사능에의한 피폭은 대부분 지표에 침척된 Cs-134 와 Cs-137으로부터 방출되는 감마선 때문이었다. KfK주변환경에서의 유효선량당량은 ICRP의 권고제한치보다 훨씬 적은 값이었다.

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Evaluation of Exposure Dose and Working Hours for Near Surface Disposal Facility

  • Yeseul Cho;Hoseog Dho;Hyungoo Kang;Chunhyung Cho
    • 방사성폐기물학회지
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    • 제20권4호
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    • pp.511-521
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    • 2022
  • Decommissioning of nuclear power plants generates a large amount of radioactive waste in a short period. Moreover, Radioactive waste has various forms including a large volumes of metal, concrete, and solid waste. The disposal of decommissioning waste using 200 L drums is inefficient in terms of economics, work efficiency, and radiation safety. Therefore, The Korea Radioactive Waste Agency is developing large containers for the packaging, transportation, and disposal of decommissioning waste. Assessing disposability considering the characteristics of the radioactive waste and facility, convenience of operation, and safety of workers is necessary. In this study, the exposure dose rate of workers during the disposal of new containers was evaluated using Monte Carlo N-Particle Transport code. Six normal and four abnormal scenarios were derived for the assessment of the dose rate in a near surface disposal facility operation. The results showed that the calculated dose rates in all normal scenarios were lower than the direct exposure dose limitation of workers in the safety analysis report. In abnormal scenarios, the work hours with dose rates below 20 mSv·y-1 were calculated. The results of this study will be useful in establishing the optimal radiation work conditions.

M&S 기반 반도체소자의 펄스감마선 피해평가 시스템 구축 연구 (A Study on Implementation of a Transient Radiation Effects on Electronics(TREE) Assessment System Based on M&S)

  • 이남호;이승민
    • 전기학회논문지
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    • 제62권7호
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    • pp.969-973
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    • 2013
  • To simulate the effect of high dose-rate radiation on semiconductor devices, device modeling work has been performed especially in the area of photo-current generation by a PIN diode. The resultant analytical values were compared with experimental ones that were specially designed and performed to benchmark the simulation results. Initial results showed 27.85% error between the simulation and the experiment. The error can be further reduced by improvement both in simulation and in related experiments. The developed technique from the study can be applicable to radiation dosimetry and to analysis on the radiation effects in electronics.

국내 원자력발전소 주변 주민의 방사선량 평가를 위한 음식물 섭취율 설정 연구 (A Study on the Food Consumption Rates for Off-site Radiological Dose Assessment around Korean Nuclear Power Plants)

  • 이갑복;정양근
    • Journal of Radiation Protection and Research
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    • 제33권4호
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    • pp.183-196
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    • 2008
  • 원전주변의 주민에 대한방사선량의 대부분을 음식물 섭취에 의한 내부피폭이 차지하고 있다. 그러나 우리나라 원전에 적용하고 있는 음식물 섭취 관련 인자는 1989년 한국원자력연구소가 고리원전 주변지역을 대상으로 수행한 현장조사 결과를 계속 적용하고 있어 최근의 식습관 변화를 적절히 반영하지 못하고 있다. 또한 우리나라는 미국 NRC (Nuclear Regulatory Commission) 에서 적용하고 있는 최대개인에 근거하여 음식물 섭취율을 결정하고 있다. 그러나 최근의 ICRP (International Commission on Radiological Protection) 의 권고 및 유럽의 관련 지침에서는 결정집단 또는 결정집단을 대표하는 개인에 대해 선량을 평가토록 권고하고 있다. 따라서 이러한 식습관의 변화추이나 피폭평가대상에 대한 국제적인 권고기준에 준하는 음식물 섭취율 설정방법에 대한연구가 필요하다. 보건복지가족부에서는 국민건강증진법에 의거 매 3년마다 전국 규모의 국민의 식품 및 영양섭취실태 조사를 실시하고 있다. 따라서 본 연구에서는 이러한 정부조사자료를 활용하여 주기적으로 음식물 섭취량 자료를 갱신할 수 있는 방안을 연구하였다. 보건복지가족부에서 $2001{\sim}2002$년에 수행한 국민영양조사원자료(raw data)를 분석하여 결정집단을 대표하는 개인의 음식물 섭취율을 결정하는데 이용할 수 있는 기초통계량을 제시하고, 또한 현재 국내 원전에서 적용하고 있는 최대개인의 음식물 섭취율을 재설정하였다.