• Journal of Radiation Protection and Research
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• 제37권3호
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• pp.129-137
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• 2012

국제방사선방호위원회(ICRP)는 2007년 발행된 ICRP 103 권고를 통해, 행위와 개입으로 대변되는 방사선방호 지침을 각 피폭상황 별로 적용하도록 변경하여 권고하였다. 이 지침에는 계획피폭상황에서 방사선방호 최적화의 수단으로 방사선작업종사자와 일반인에 대해 선원중심의 선량제약치(dose constraint)를 설정하여 운영하도록 권고하고 있다. 이 논문에서는 계획피폭상황에서 일반인 선량제약치를 설정하는데 필요한 국내 원전의 방사성물질의 배출량과 이에 따른 주변주민의 피폭방사선량 평가 결과를 분석하였다. 이를 바탕으로 국내 원전의 동일부지 내 복수호기 원전의 운영을 고려한 선량제약치 설정 방안을 제시하였다.

• Journal of Radiation Protection and Research
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• 제6권1호
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• pp.31-33
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• 1981

The 42 patients with carcinoma of the cervix, performed intracavitary radiotherapy, were analysed the doses at points A and B comparing to the mghr prescription. The doses at points A and B were calculated by PC-12 computer planning system. Correlation coefficienty between doses at points A and B and the mghr prescription are 0.82 (p<0.001) and 0.90 (p<0.001) respectively. The slope of the point A line is 0.70 and the slope of the point B is 0.21. Therefore, the dose at point A is approximately 3/4 the mghr prescription and the dose at point B is approximately 1/4 the mghr precription.

• Journal of Radiation Protection and Research
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• 제48권2호
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• pp.84-89
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• 2023

Background: Food consumption is one of the most important routes for radionuclide intake for the public; therefore, there is the need to have a comprehensive understanding of the amount of radioactivity in food products. Consumption of radionuclide-contaminated food could increase potential health risks associated with exposure to radiation such as cancers. The present study aims to determine radioactivity levels in some food products (milk, rice, sugar, and wheat flour) consumed in Mali and to evaluate the radiological effect on the public health from these radionuclides. Materials and Methods: The health impact due to ingestion of radionuclides from these foods was evaluated by the determination of activity concentration of radionuclides ²³⁸U, ²³²Th, ⁴⁰K, and ¹³⁷Cs using gamma spectrometry system with high-purity germanium detector and radiological hazards index in 16 samples collected in some markets, mall, and shops of Bamako-Mali. Results and Discussion: The average activity concentrations were 9.8±0.6 Bq/kg for ²³⁸U, 8.7±0.5 Bq/kg for ²³²Th, 162.9±7.9 Bq/kg for ⁴⁰K, and 0.0035±0.0005 Bq/kg for ¹³⁷Cs. The mean values of radiological hazard parameters such as annual committed effective dose, internal hazard index, and risk assessment from this work were within the dose criteria limits given by international organizations (International Commission on Radiological Protection and United Nations Scientific Committee on the Effects of Atomic Radiation) and national standards. Conclusion: The results show low public exposure to radioactivity and associated radiological impact on public health. Nevertheless, this study stipulates vital data for future research and regulatory authorities in Mali.

• 한국방사선학회논문지
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• 제13권3호
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• pp.439-444
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• 2019

본 연구에서는 강력한 항산화제로 알려진 셀레늄의 방사선방호효과를 연구하였다. 렛드에 셀레늄을 14일간 경구투여 후 10 Gy의 방사선을 전신조사하였다. 그리고 1일, 3.5일, 7일, 21일 후에 혈구 성분 및 SOD(Superoxide Dismutase)와 소장의 변화를 관찰하였다. 방사선조사군에 비해 셀레늄 투여 후 방사선조사군에서 조혈면역계의 손상을 경감시키는 유의한 방호 효과가 있었다(p<0.05). 그리고 셀레늄이 항산화 효소인 Superoxide Dismutase(SOD)의 활성을 증가시키는 유효한 성분이며, 방사선 조사에 의한 소장움 세포의 apoptosis 발현을 억제하는 효과가 있음을 확인하였다. 이 결과를 바탕으로 셀레늄은 방사선으로부터 생명체를 보호하는 필수 성분이라 생각한다.

• Journal of Radiation Protection and Research
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• 제29권1호
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• pp.49-55
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• 2004

This paper presents the mechanical and thermal stress analysis of a disposal canister to provide basic information for dimensioning the canister and configuration of the canister components. The structural stress analysis is carried out using a finite element analysis code, NISA, and focused on the structural strength of the canister against the expected external pressures due to the swelling of the bentonite buffer and the hydrostatic head, and the thermal load build up in the container.

• Journal of Radiation Protection and Research
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• 제15권2호
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• pp.101-112
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• 1990

For the performance assessment of the radioactive waste disposal system (repository), a biosphere model is suggested. This biosphere model is intended to calculate the annual doses to man caused by the contaminated river water for eight pathways and four radionuclides. This model can also be applied to assess the radiological effects of contaminated well water. To account for the uncertainties on the model parameter values, parameter distributions are assigned to these model parameters. Then, Monte Carlo simulation method with Latin Hypercube sampling technique is used. Also, sensitivity analysis is performed by using the Spearman rank correlation coefficients. It is found that these methods are a very useful tool to treat uncertainties and sensitivities on the model parameter values and to analyze the biosphere model. A conversion factor is proposed to calculate the annual dose rate to humans arising from a unit radionuclide concentration in river water. This conversion factor allows for the substitution of the biosphere model in a probabilistic performance assessment computer code by one single variable.

• Journal of Radiation Protection and Research
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• 제17권2호
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• pp.37-48
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• 1992

월성 원자력 발전소 2호기의 1차 종단 및 측면 차폐 계통의 각 차폐체에 대한 100% 출력 가동시 핵에너지 축적을 해석을 ANISN 코드를 이용하여 수행하였다. 본 해석 결과는 월성원자력 발전소 2호기 계통 설계시 고려 사항으로 이용될 수 있다.

• Journal of Radiation Protection and Research
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• 제28권3호
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• pp.173-182
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• 2003

베타선 방출 핵종 측정을 위한 프로토 타입(prototype) 액체섬광검출기를 개발하고 이의 특성을 분석하였다. 액체섬광계수시스템의 신호처리부는 2개의 광전자증배관(photomultiplier tube, PMT)과 동시 계수 회로를 이용하여 구성하였다. 제작한 프로토 타입 시스템의 특성 분석을 위하여 4종류의 베타 핵종 $(^3H,\;^{14}C,\;^{36}Cl,\;^{90}Sr)$에 대한 샘플을 조제하여 베타 스펙트럼을 측정하였다. 차폐체를 전혀 사용하지 않은 상태에서 측정한 4종류의 핵종에 대한 베타 스펙트럼을 구하고, 최소 검출 한계를 계산한 다음, 법적 규제치 및 계산된 검출한계와 비교하였다. 이들 대부분의 선원들은 수분이내의 측정으로 배수중 방사선물질에 대한 법적 규제치 이하로 충분히 검출 가능함을 확인하였다.

• Journal of Radiation Protection and Research
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• 제42권2호
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• pp.106-113
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• 2017

Background: Interfacing-system loss-of-coolant-accident (ISLOCA) has been identified as the most hazardous accident scenario in the typical PWR plants. The present study as an effort to improve the knowledge of the source term to the environment during ISLOCA focuses on an improvement of the estimation method. Materials and Methods: The improvement was performed to take into account an effect of broken pipeline and auxiliary building structures relevant to ISLOCA. An estimation of the source term to the environment was for the OPR-1000 plants by MELOCR code version 1.8.6. Results and Discussion: The key features of the source term showed that the massive amount of fission products departed from the beginning of core degradation to the vessel breach. Conclusion: The release amount of fission products may be affected by the broken pipeline and the auxiliary building structure associated with release pathway.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.161-165
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• 2001

We have developed a position-sensitive proton recoil telescope (PSPRT) which employs a position-sensitive photomultiplier (PS-PMT) and a scintillator for both a radiator and a proton-detector. This system is expected to achieve high energy resolution under a large solid angle, because it enables to obtain the information not only on the proton energy but also the recoil angle from the position data for both detectors. The response of the PSPRT for 14.1 MeV mono-energetic neutrons was measured, and the PSPRT proved to be operating as expected.