• Journal of Radiation Protection and Research
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• 제47권1호
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• pp.39-49
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• 2022

Background: For proper monitoring of the eye lens dose, an appropriate calibration factor of a dosimeter and information about the mean energies of X-rays are indispensable. The scattered X-ray energy spectra should be well characterized in medical practices where eye lenses of medical staffs might be high. Materials and Methods: Scattered X-ray energy spectra were experimentally derived for three different types of X-ray diagnostic and therapeutic equipment, i.e., the computed tomography (CT) scan, the angiography and the fluoroscopy. A commercially available CdZnTe (CZT) spectrometer with a lead collimator was employed for the measurement of scattered X-rays, which was performed in the usual manner. Results and Discussion: From the obtained energy spectra, the mean energies of the scattered X-rays lied between 40 and 60 keV. This also agreed with that obtained by the conventional half value layer method. Conclusion: The scattered X-rays to which medical workers may be exposed in the region around the eyes were characterized by means of spectrometry. The obtained mean energies of the scattered X-rays were found to match the flat region of the dosimeter response.

• 환경생물
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• 제21권4호
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• pp.321-327
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• 2003

Differences between the principles for the radiological protection of man and the environment are compared. The derived levels of exposure for man and biota recommended by the international agencies with dose rates for chronic radiation producing effects at different levels of biological organization were given in terms of the biological effects. Cytogenetic effects on plants after an exposure to ionizing radiation at low doses alone and in combination with other factors are discussed. A wide range of experimental data were analysed and the general conclusions were extracted to cover the topics such as non-linearity of dose response, synergistic and antagonistic effects of the combined exposure of different factors, radiation-induced genomic instability, and the phenomena of radioadaptation.

• 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.

• Journal of Radiation Protection and Research
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• 제34권3호
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• pp.115-120
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• 2009

1990년대 이후부터 현재까지 일련의 사건들은 - 1995년 러시아 국립공원에서 매설된 오염폭탄발견, 2001년 9/11 테러, 2003년 알카에다 오염폭탄 실험 증거 발견등 - 방사성물질 (본 논문에서 언급한 "방사성물질"은 "핵물질 사용후핵연료 방사성동위원소"를 말함)을 이용한 핵테러 및 방사능테러 (본 논문에서는 "핵테러 및 방사능테러"를 간단히 "핵테러/방사능테러"로 표시함)가 공상과학소설이 아닌 실제적으로 발생가능할 심각한 위협임을 보여준다. 이에 따라 세계는 새롭게 대두된 위협에 효과적으로 대응하기 위해 방사성물질에 대한 보안(security)과 물리적방호(physical protection)를 강화하고 방사성물질 불법거래 예방 및 대응체제를 구축하도록 요구하고 있다. 우리나라는 이러한 국제적 추세에 부응하기 위해, 관련 법 체제를 제 개정하고 국제협약 혹은 기구에 합의하거나 가입하였다. 본 논문에서는 핵테러/방사능테러 예방의 일환으로 방사성동위원소에 비해 상대적으로 복잡한 붕괴 과정을 가진 핵물질의 물리적 특성을 살펴보고, 현재 운영되고 있는 핵테러/방사능테러 탐지 장비들의 특성을 파악한다. 검토된 장비들의 특성과 함께 국외에서 국내로 불법 유입된 방사성물질이 목표 지점까지 도달되는 과정, 국내 지형적 특정 그리고 다중 방어적 개념을 고려하여 핵테러/방사능테러 탐지체계 구축 방안을 제안한다. 본 논문은 핵테러/방사능테러로부터 국민의 건강, 안전 그리고 환경을 보호하는데 중요한 기여를 할 것으로 판단된다.

• 대한방사선기술학회지:방사선기술과학
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• 제41권6호
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• pp.581-586
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• 2018

This study was conducted to analyze factors Influencing Protective Behavior against Radiation Exposure using questionnaires for 231 radiological technologists working in Computed Tomography(CT) examination room with high radiation dose in diagnostic radiology field. Statistical analysis of the collected data revealed that the reasons for partially shielding the examination part in the CT scan were the lack of protective equipment, securing of radiation justification, being annoying and maybe not being harm to adults in order. It was also revealed that the variables influencing the protective behavior were protective behavior against radiation harm, self-efficacy, protective environment, organization culture, protective knowledge and protective instrument in order. The higher the radiological protective environment(${\beta}=0.245$) and the lower the radiological protective knowledge(${\beta}=-0.034$), the more influential the protective behavior against radiation harm was. In this study, it was shown that non examination parts were not shielded in the CT scan. Therefore, it is necessary to improve the level of protective environment, to cultivate knowledge to improve the protective behavior against radiation harm and to have an intervention strategy for concrete action.

• Journal of Radiation Protection and Research
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• 제38권4호
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• pp.179-184
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• 2013

The biological effects of radiation are dependent on the dose rate and dose of radiation. In this study, effects of dose and dose rate using whole body radiation on plasma cytokines and blood count from male BALB/c mice were evaluated. We examined the blood and cytokine changes in mice exposed to a low (3.49m Gy $h^{-1}$) and high (2.6 Gy $min^{-1}$) dose rate of radiation at a total dose of 0.5 and 2 Gy, respectively. Blood from mice exposed to radiation were evaluated using cytokine assays and complete blood count. Peripheral lymphocytes and neutrophils decreased in a dose dependent manner following high dose rate radiation. The peripheral lymphocytes population remained unchanged following low dose rate radiation; however, the neutrophils population increased after radiation. The sera from these mice exhibited elevated levels of flt3 ligand and granulocyte-colony-stimulating factor (G-CSF), after high/low dose rate radiation. These results suggest that low-dose-rate radiation does not induce blood damage, which was unlike high-dose-rate radiation treatment; low-dose-rate radiation exposure activated the hematopoiesis through the increase of flt3 ligand and G-CSF.

• Journal of Radiation Protection and Research
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• 제28권1호
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• pp.25-33
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• 2003

악성 종양 진단에 사용되고 있는 방사성 동위원소 $^{67}Ga$의 대량생산을 위한 자동화장치를 개발하였다. $^{67}Ga$은 조사된 $^{68}Zn$ 농축타켓에서 분리 생산하며 생산방법으로는 크게 용매추출법과 이온수지 법이 이용된다. 분리과정을 자동화하기 위해서 전도도 측정 장치, 화학처리 초자, 에어 공급 및 용액공급튜브, 밸브들로 이루어진 분액장치와, 이 장치를 구동하고 제어하는 PLC 기반 콘트롤러 및 사용자 직접제어용 모니터링 장치로 구성된 시스템을 개발하였다. 개발된 시스템을 사용함으로써 생산 중에 발생되는 불필요한 방사선 피폭으로부터 생산자를 보호할 뿐만 아니라, 생산시간의 단축, 생산효율의 증대로 $^{67}Ga$ 대량 생산이 가능하게 되었다.

• Journal of Radiation Protection and Research
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• 제46권2호
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• pp.39-47
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• 2021

Background: The National Institutes for Quantum and Radiological Science and Technology-National Institute of Radiological Sciences (QST-NIRS) has continuously investigated the undesired radiation exposure in ion beam radiotherapy mainly in carbon-ion radiotherapy (CIRT). This review introduces our investigations on the secondary neutron dose in CIRT with the broad and scanning beam methods. Materials and Methods: The neutron ambient dose equivalents in CIRT are evaluated based on rem meter (WENDI-II) measurements. The out-of-field organ doses assuming prostate cancer and pediatric brain tumor treatments are also evaluated through the Monte Carlo simulation. This evaluation of the out-of-field dose includes contributions from secondary neutrons and secondary charged particles. Results and Discussion: The measurements of the neutron ambient dose equivalents at a 90#x00B0; angle to the beam axis in CIRT with the broad beam method show that the neutron dose per treatment dose in CIRT is lower than that in proton radiotherapy (PRT). For the scanning beam with the energy scanning technique, the neutron dose per treatment dose in CIRT is lower than that in PRT. Moreover, the out-of-field organ doses in CIRT decreased with distance to the target and are less than the lower bound in intensity-modulated radiotherapy (IMRT) shown in AAPM TG-158 (American Association of Physicists in Medicine Task Group). Conclusion: The evaluation of the out-of-field doses is important from the viewpoint of secondary cancer risk after radiotherapy. Secondary neutrons are the major source in CIRT, especially in the distant area from the target volume. However, the dose level in CIRT is similar or lower than that in PRT and IMRT, even if the contributions from all radiation species are included in the evaluation.

• Journal of Radiation Protection and Research
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• 제45권2호
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• pp.88-94
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• 2020

Background: The International Commission on Radiological Protection (ICRP) has recently published report series on the occupational intakes of radionuclides (OIR) for internal dosimetry of radiation workers. In this study, the optimized monitoring program including the monitoring interval and the minimum detectable activity (MDA) of major radionuclides was suggested to perform the routine individual monitoring of internal exposure based on the ICRP OIR. Materials and Methods: The derived recording levels and the critical monitoring quantities were reviewed from international standards or guidelines by the International Atomic Energy Agency (IAEA), the International Organization for Standardization (ISO), and the European Radiation Dosimetry Group (EURADOS). The OIR data viewer provided by ICRP was used to evaluate the monitoring intervals and the MDA, which are derived from the reference bioassay functions and the dose coefficients. Results and Discussion: The optimal monitoring intervals were determined taking account of two requirement conditions on the potential intake underestimation and the MDA values. The MDA requirement values of the selected radionuclides were calculated based on the committed effective dose from 0.1 mSv to 5 mSv. The optimized routine individual monitoring program was suggested including the optimal monitoring intervals and the MDA requirements. The optimal MDA values were evaluated based on the committed effective dose of 0.1 mSv. However, the MDA can be adjusted considering the practical operation of the routine individual monitoring program in the nuclear facilities. Conclusion: The monitoring intervals and the MDA as crucial factors for the routine monitoring were described to suggest the optimized routine individual monitoring program of the occupational intakes. Further study on the alpha/beta-emitting radionuclides as well as short lived gamma-emitting nuclides will be necessary in the future.

• 대한방사선기술학회지:방사선기술과학
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• 제33권4호
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• pp.321-326
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• 2010

본 연구에서는 미역이나 다시마에 많이 분포하면서 항산화작용이 탁월한 알긴산올리고당의 방사선 방어효과를 알아보기 위해 3 Gy 방사선이 전신 1회 조사된 마우스를 가지고 IL-6을 측정하였다. 측정 결과 방사선조사대조군과 비교하여 볼 때 소장과 간 조직 모두 방사선조사 전 7일간 알긴산올리고당의 처치를 시행한 그룹에서 IL-6 생성이 억제됨을 관찰하였다(p < 0.001). 이는 알긴산올리고당이 항산화작용을 통해 방사선이 피폭된 생체조직을 방어함으로써 IL-6의 생성을 억제한 것으로 사료된다. 결론적으로, 본 연구를 통해 알긴산올리고당의 일부 방사선 방어효과를 규명했고 아울러 화학적 독성이 없는 자연산생물이 방사선 방어제로 활용될 수 있을 가능성을 확인하였다.