• 한국산학기술학회논문지
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• 제10권7호
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• pp.1760-1765
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• 2009

의료기관 핵의학과에서는 진단과 치료를 목적으로 방사성동위원소를 사용하므로 누구나 방사선피폭에 노출 될 위험이 있다. 일반적으로 방사선 작업종사자에 대한 피폭관리는 비교적 철저히 이루어지고 있으나 환자보호자 및 일반인에 대한 피폭관리는 소홀한 경향이 있다. 특히 방사성의약품을 투여한 환자들은 잠재적 선원이 되어 작업종사자외에 환자보호자 및 일반인에 대해 방사선피폭을 초래하므로 이로 인한 방사선피폭을 최소한으로 감소시킬 수 있도록 관리되어야 한다. 따라서 핵의학과 방사선피폭에 대한 관리실태를 파악하기 위하여 전국에 있는 대학병원 중 7개소에 대해 조사한 결과 환자이송요원, 환경미화원 등 수시출입자에 대해서 2 개소의 의료기관에서는 피폭선량평가 및 관리와 안전교육이 없었다. 또한 환자와 동행하는 보호자에 대한 통제와 관리는 7 개소 모두 허술하였는데 대기실에서 검사직전 환자로부터 흡수될 수 있는 평균 방사선량률은 25.60 ${\mu}$Sv/h로서 일반인에 대해 연간 선량한도를 초과하지 아니하는 범위 내에서 허용되는 20 ${\mu}$Sv/h를 초과하였다. 따라서 비록 아주 적은 피폭선량이 예상된다고 하더라도 수시출입자에 대한 철저한 피폭선량의 관리와 교육이 요구되며, 환자보호자 등을 보호하기 위해 환자와 가까이 하는 것을 통제하거나 환자를 격리할 필요가 있었다.

• 방사선산업학회지
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• 제8권1호
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• pp.49-52
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• 2014

Kenaf fibers have excellent properties and possess the potential to be outstanding reinforcing fillers in cement. The grafting of poly(ethylene glycol) methacrylate (PEGMA) to the kenaf fibers is important in improving the compatibility between the fibers and the cement. PEGMA was grafted onto kenaf fibers using gamma-ray radiation. The radiation dose ranged from 20 to 60 kGy, and the dose rate was $10kGy\;h^{-1}$. The degree of grafting increased with increased radiation doses. FT-IR analysis revealed an increase in PEGMA content after gamma-ray radiation induced grafting, further evincing the attachment of PEGMA to the kenaf fibers. The mechanical properties of the gamma-ray grafted kenaf fiber/cement composites were superior to those of the ungrafted kenaf fiber/cement specimens.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2410-2414
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• 2020

Heavy ions have a high potential for destroying deep tumors that carry the highest dose at the peak of Bragg. The peak caused by a single-energy carbon beam is too narrow, which requires special measures for improvement. Here, carbon-12 (¹²C) ion with different energies has been used as a source for calculating the dose distribution in the water phantom, soft tissue and bone by the code of Monte Carlobased FLUKA code. By increasing the energy of the initial beam, the amount of absorbed dose at Bragg peak in all three targets decreased, but the trend for this reduction was less severe in bone. While the maximum absorbed dose per bone-mass unit in energy of 200 MeV/u was about 30% less than the maximum absorbed dose per unit mass of water or soft tissue, it was merely 2.4% less than soft tissue in 400 MeV/u. The simulation result showed a good agreement with experimental data at GSI Darmstadt facility of biophysics group by 0.15 cm average accuracy in Bragg peak positioning. From 200 to 400 MeV/u incident energy, the Bragg peak location increased about 18 cm in soft tissue. Correspondingly, the bone and soft tissue revealed a reduction dose ratio by 2.9 and 1.9. Induced neutrons did not contribute more than 1.8% to the total energy deposited in the water phantom. Also during ¹²C ion bombardment, secondary fragments showed 76% and 24% of primary 200 and 400 MeV/u, respectively, were present at the Bragg-peak position. The combined treatment of carbon ions with neutron or electron beams may be more effective in local dose delivery and also treating malignant tumors.

• 한국임상수의학회지
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• 제41권3호
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• pp.157-164
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• 2024

The standard radiation protection method in the angiography suite involves the use of a thyroid shield, a lead apron, and lead glasses. However, exposure to substantial amounts of ionizing radiation can cause cataracts, tumors, and skin erythema. A newly developed curtain-type radiation protection device consists of a curtain drape composed of a five-layer bismuth and lead acrylic head-shielding plate, with both bearing an equivalent 0.25 mm lead thickness. In this study, a quality assurance phantom was used as the patient to create radiation scatter from the radiographic source, and an anthropomorphic mannequin phantom was used as the interventionalist to measure the radiation dose at seven different anatomical locations. Thermoluminescent dosimeters were used to measure the radiation dose. The experimental groups consisted of all-sided or one-sided curtain set-ups, the presence or absence of a conventional shielding system, and the orientation of beam irradiation. Consequently, the curtain-type radiation protection device exhibited better radiation protection range and capabilities than conventional radiation protection systems, especially in safeguarding the forehead, eyes, arms, and feet, with minimal radiation exposure. Moreover, the mean shielding ratios of the conventional shielding system and curtain-type radiation protection device were measured at 51.94% and 93.86%, respectively. Additionally, no significant decrease in the radiation protection range or capability was observed, even with changes in the beam orientation or one-sided protection. Compared with a conventional shielding system, the curtain-type radiation protection device decreased radiation exposure doses and improved comfort. Therefore, it is a potential new radiation protection device for veterinary interventional procedures.

• Journal of Radiation Protection and Research
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• 제31권3호
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• pp.135-140
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• 2006

비밀봉 방사성물질의 취급 사고시 방사성핵종은 흡입과 취식의 두 가지 경로로 섭취될 수 있다. 이때 일상 감시처럼 하나의 섭취경로만 가정하여 예탁유효선량을 평가하면 심각한 오차를 유발할 수 없다. 이러한 잠재 오차를 제시하기 위해 총 섭취에 대한 흡입섭취의 비율을 달리할 때 예탁유효선량의 변동을 분석하였다. $^{241}Am$(AMAD 5 ${\mu}m$, 흡수형 M)을 대상으로 핵종의 생물역동학적 모델과 데이터를 이용하여 여러 흡입섭취 분율에서 폐, 소변 및 대변에 대한 바이오어세이 측정치를 모의하였다. 섭취 3일 후 예상 측정치를 이용하고 단일 경로 섭취를 가정한 경우 평가된 예탁유효선량의 잠재 오차는 -100%에서부터 많게는 +34,000%에 이르는 것으로 나타났다. 흡입섭취가 있을 때 대변만 분석하면 큰 오차가 발생하였다. 섭취경로 오판에 따르는 선량평가의 오차를 줄이기 위해 두 종류의 바이오어세이를 이용하는 전략을 제안하였다.

• Radiation Oncology Journal
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• 제37권4호
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• pp.265-270
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• 2019

Purpose: Renal cell carcinoma (RCC) and melanoma have been considered 'radioresistant' due to the fact that they do not respond to conventionally fractionated radiation therapy. Stereotactic radiosurgery (SRS) provides high-dose radiation to a defined target volume and a limited number of studies have suggested the potential effectiveness of SRS in radioresistant histologies. We sought to determine the effectiveness of SRS for the treatment of patients with radioresistant brain metastases. Materials and Methods: We performed a retrospective review of our institutional database to identify patients with RCC or melanoma brain metastases treated with SRS. Treatment response were determined in accordance with the Response Evaluation Criteria in Solid Tumors. Results: We identified 53 radioresistant brain metastases (28% RCC and 72% melanoma) treated in 18 patients. The mean target volume and coverage was 6.2 ± 9.5 mL and 95.5% ± 2.9%, respectively. The mean prescription dose was 20 ± 4.9 Gy. Forty lesions (75%) demonstrated a complete/partial response and 13 lesions (24%) with progressive/stable disease. Smaller target volume (p < 0.001), larger SRS dose (p < 0.001), and coverage (p = 0.008) were found to be positive predictors of complete response to SRS. Conclusion: SRS is an effective management option with up to 75% response rate for radioresistant brain metastases. Tumor volume and radiation dose are predictors of response and can be used to guide the decision-making for patients with radioresistant brain metastases.

• 센서학회지
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• 제9권3호
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• pp.213-223
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• 2000

원자력 관련시설이나 우주 공간, 방사선 치료 센터 등에서 발생되는 방사선량은 정확히 검출되어야 할 필요성이 있다. 본 논문에서는 상용 P채널 Power MOSFET(metal oxide field effect transistor)를 방사선 누적선량 모니터링 센서로 활용하기 위해 실시간 방사선량 검출 측정 시스템을 설계 제작하였고, 시스템의 성능을 분석하기 위하여 Co-60 $\gamma$선원을 갖춘 고준위 조사시설에서 조사한 후 출력특성의 변화를 분석하였다. 방사선 조사실험 결과 P채널 Power MOSFET은 조사된 누적 방사선량에 비례하여 문턱전압($V_T$)이 변화됨과 곡선 변화의 선형적 특성을 지님을 알 수 있었다. 이 선형 함수관계를 이용하여 저가의 상용 P채널 Power MOSFET를 사용한 방사선 총 누적선량을 모니터링하기 위한 센서로 사용할 수 있음을 확인하였다.

• 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.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2198-2203
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• 2022

As robotics become more sophisticated, there are a growing number of generic systems being used for routine tasks in nuclear environments to reduce risk to radiation workers. The nuclear sector has called for more commercial-off-the-shelf (COTS) devices and components to be used in preference to nuclear specific hardware, enabling robotic operations to become more affordable, reliable, and abundant. To ensure reliable operation in nuclear environments, particularly in high-gamma facilities, it is important to quantify the tolerance of electronic systems to ionizing radiation. To deliver their full potential to end-users, mobile robots require sophisticated autonomous behaviors and sensing, which requires significant computational power. A popular choice of computing system, used in low-cost mobile robots for nuclear environments, is the UP Core single board computer. This work presents estimates of the total ionizing dose that the UP Core running the Robot Operating System (ROS) can withstand, through gamma irradiation testing using a Co-60 source. The units were found to fail on average after 111.1 ± 5.5 Gy, due to faults in the on-board power management circuitry. Its small size and reasonable radiation tolerance make it a suitable candidate for robots in nuclear environments, with scope to use shielding to enhance operational lifetime.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.429-436
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• 2022

Investigations of retrospective dosimetry have shown that components of mobile phones are suitable as emergency dosimeters in case of radiological incidents. For physical dosimetry, components can be read out using optically stimulated luminescence (OSL), thermoluminescence (TL) and phototransferred thermoluminescence (PTTL) methods to determine the absorbed dose. This paper deals with a feasibility study of display glass from modern mobile phones that are measured by thermally assisted (Ta) optically stimulated luminescence. Violet (VSL, 405 nm) and infrared (IRSL, 850 nm) LEDs were used for optical stimulation and two protocols (Ta-VSL and Ta-IRSL) were tested. The aim was to systematically investigate the luminescence properties, compare the results to blue stimulated Ta-BSL protocol (458 nm) and to develop a robust measurement protocol for the usage as an emergency dosimeter after an incident with ionizing radiation. First, the native signals were measured to calculate the zero dose signal. Next, the reproducibility and dose response of the luminescence signals were analyzed. Finally, the signal stability was tested after the storage of irradiated samples at room temperature. In general, the developed Ta-IRSL and Ta-VSL protocols indicate usability, however, further research is needed to test the potential of a new protocol for physical retrospective dosimetry.