• 방사성폐기물학회지
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• 제18권spc호
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• pp.75-87
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• 2020

The Korea Atomic Energy Research Institute (KAERI) has developed geological repository systems for the disposal of high-level wastes and spent nuclear fuels (SNFs) in South Korea. The purpose of the most recently developed system, the improved KAERI Reference Disposal System Plus (KRS⁺), is to dispose of all SNFs in Korea with improved disposal area efficiency. In this paper, a system-level safety assessment model for the KRS⁺ is presented with long-term assessment results. A system-level model is used to evaluate the overall performance of the disposal system rather than simulating a single component. Because a repository site in Korea has yet to be selected, a conceptual model is used to describe the proposed disposal system. Some uncertain parameters are incorporated into the model for the future site selection process. These parameters include options for a fractured pathway in a geosphere, parameters for radionuclide migration, and repository design dimensions. Two types of SNF, PULS7 from a pressurized water reactor and Canada Deuterium Uranium from a heavy water reactor, were selected as a reference inventory considering the future cumulative stock of SNFs in Korea. The highest peak radiological dose to a representative public was estimated to be 8.19×10^-4 mSv·yr^-1, primarily from ¹²⁹I. The proposed KRS⁺ design is expected to have a high safety margin that is on the order of two times lower than the dose limit criterion of 0.1 mSv·yr^-1.

• 한국방사선학회논문지
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• 제11권6호
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• pp.423-428
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• 2017

본 연구에서는 몬테카를로 전산해석법으로 K대학교 진료영상 촬영 실습실의 방사선 조사실과 발생장치 제어실 내부 공간 유효선량률 분포 계산을 수행하였다. 방사선 발생장치는 최대 관전압 150 kVp에 최대 관 전류 700 mA이다. 전산해석 결과를 이용하여 차폐문이 닫힌 경우와 열린 경우의 진료영상 촬영 실습실의 공간선량 분포를 비교 평가하였다. 결과적으로, 차폐문이 열린 경우에도 방사선 발생장치 제어실의 유효선량률은 학생(수시출입자)의 연간 유효선량률 한도(6 mSv/y)를 초과하지 않는다는 것을 알 수 있었다. 하지만, 차폐문이 열려있을 때의 유효선량률이 차폐문이 닫힌 경우에 비해 납유리 앞에서는 약 16배, 차폐문 앞에서는 약 3,000배 더 높기 때문에 실습 중에 차폐문을 닫는 것이 불필요한 방사선 피폭을 크게 줄인다는 것을 알 수 있었다.

• 대한방사선기술학회지:방사선기술과학
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• 제42권1호
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• pp.61-66
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• 2019

The purpose of this study was to improve the unstable treatment posture by placing the Carbon fabric blanket on the couch which was used for the patient fixation for the unstable posture from the severe pain caused by the neuromuscular pressure of the spinal metastatic cancer patient and to analyze the dose difference caused by the energy loss of high energy radiation. Using a linear accelerator, a FC-65G was installed at a depth of 5 cm at a solid phantom at 6 MV and 10 MV energies. The SAD was 100 cm, Gantry angle was $0^{\circ}$, a Cotton and Carbon blanket with a thickness of 1 cm on the couch, The blankets were placed on the couch and the dose was measured according to field size. For the dose measurement, and the dose was measured at 100 MU each time, and the mean value was calculated by repeating the measurement three times in order to reduce the error. The results showed that the difference rate in dose between Carbon blanket and Cotton blanket was respectively -0.54% and -0.75% based on the absence of the blanket(Non). Therefore, it is considered that the use of Carbon fabric blanket, which reduces the patient's pain and does not affect the depth dose, may be useful during radiation therapy of the spine metastasis cancer.

• 대한방사선기술학회지:방사선기술과학
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• 제47권2호
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• pp.107-116
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• 2024

In this study, we analyzed the use of general radiography imaging and effective dose in inpatients. Our aim is to help reduce national medical radiation exposure doses and develop rational health-care financial policies. The effective dose for each general radiography was calculated using the ALARA-GR program for 53 types (total: 260 codes) general radiography codes selected from 'National Health Insurance Care Benefit Cost'. The usage of general radiography was analyzed in the 2018 inpatient patient data of the Health Insurance Review and Assessment Service, and the effective dose for each general radiography was analyzed. 89.00% of inpatients undergo general radiography imaging at least once, with an average of 12.63 scans per person and an effective dose of 1.00 mSv. Those who received support from Medical Aid showed a higher value compared to those who were insured by National Health Insurance, with 17.39 cases and 1.43 mSv (p<.001). Chest had the highest usage rate at 23.12% for general radiography imaging, while L-spine had the highest effective dose at 24.53%. It is estimated that 420 inpatients patients undergo 121 to 820 general radiography imaging procedures per year, and 233 inpatients are estimated to have an annual effective dose of >20.00~58.25 mSv. Rational use of health-care finances and the practice of medical radiation safety management are essential for the well-being of individuals, the enhancement of quality of life, and the improvement of health-care quality.

• 한국방사선학회논문지
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• 제17권3호
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• pp.367-373
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• 2023

비행시 승무원이나 승객은 우주방사선과 공기나 비행기 기체와 반응하여 발생한 2차 산란선 등에 의해 피폭을 받게 된다. 항공기 승무원의 경우 우주기상 환경 시뮬레이션을 이용하여 계산된 피폭선량으로 방사선 안전관리를 적용받고 있다. 하지만, 태양활동이나 고도, 비행경로 등에 따라 피폭선량이 가변적이어서 계산법보다는 항로별 측정하는 것이 권고되고 있다. 본 연구에서는 범용 Si 센서와 다중채널파고분석기를 이용하여 우주방사선 선량을 측정할 수 있는 선량계를 개발하였다. 선량계산은 미우주항공국의 우주방사선 측정장비인 CRaTER(Cosmic Ray Telescope for the Effects of Radiation)의 알고리즘을 적용하였다. 표준교정시설에서 Cs-137 662 keV 감마선으로 에너지 및 선량교정을 시행하였으며, 실험 범위에서 선량률 의존성이 없음을 확인하였다. 제작된 선량계를 이용하여 2023년 5월 두바이 인천 구간의 국제선에서 직접 선량을 측정한 결과 국내 우주방사선 선량평가코드(KREAM; Korean Radiation Exposure Assessment Model for Aviation Route Dose)로 계산된 결과와 12% 이내로 비슷하게 나타났으며, 고도와 위도가 높아짐에 따라 계산 결과와 동일하게 선량이 증가하는 것을 확인하였다. 좀 더 많은 실증적 검증 실험이 요구되는 제한점은 있지만, 항공기 내 또는 개인 피폭선량 모니터링에 가성비가 우수한 선량계로 충분한 활용 가능성을 확인하였다.

• 대한방사선기술학회지:방사선기술과학
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• 제37권4호
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• pp.239-246
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• 2014

필터는 저에너지 X선을 흡수함으로써 평균에너지를 증가시키고, 환자의 피폭선량을 감소시키는 작용을 한다. 본 연구는 Mo과 W 등의 재질이 디지털 방사선영상장치인 CR에서도 사용이 가능한지 SNR, FOM, histogram 등의 영상평가와 선량 측정을 통해 확인하였다. 또한 필터의 재질에 따른 선질측정과 함께 관전압의 변화에 따른 적합한 필터 조합을 찾아보았다. 피부입사선량은 Mo필터가 Cu필터에 비해 42~56%까지 선량 경감효과가 있었고, 투과선량도 Mo필터가 Cu필터보다 1.5배 정도 높게 나타났다. 영상 평가에서 W은 필터로 사용함에 부적절하였으나, Mo은 80 kVp 이상의 관전압에서 영상의 질을 저하시키지 않으면서 선량을 감소시킬 수 있는 필터로 충분히 사용할 수 있음을 확인하였다. 2.0 mmAl+0.1 mmMo은 관전압이 높아질수록 2.0 mmAl + 0.2 mmCu와 histogram width가 거의 같아서, 비교적 높은 관전압인 80, 100, 120 kVp에서는 Mo필터의 사용이 가능하다. 2.0 mmAl + 0.1 mmMo의 SNR은 2.0 mmAl + 0.2 mmCu와 2.0 mmAl+0.1 mmCu의 SNR과도 큰 차이가 나지 않았다. 따라서 디지털 방사선 영상 중 80 kVp 이상을 이용하는 일반촬영에서 Cu를 대신하여 Mo을 필터로 사용하면 Cu에 비해 영상의 질을 저하시키지 않으면서 환자의 피폭선량을 크게 감소시킬 수 있으므로, 실제 임상의 흉부 촬영 및 고관전압 촬영 등에 충분히 적용할 수 있다고 본다.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1757-1762
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• 2023

Radiological hazards from external exposure of naturally occurring radioactive materials (NORM) scales residues, generated during the extraction process of oil and gas production in southern Algeria, are evaluated. The activity concentrations of ²²⁶Ra, ²³²Th, and ⁴⁰K were measured using high-purity gamma-ray spectrometry (GeHP). Mean activity concentration of ²²⁶Ra, ²³²Th and ⁴⁰K, found in scale samples are 4082 ± 41, 1060 ± 38 and 568 ± 36 Bq kg^-1, respectively. Radiological hazard parameters, such as radium equivalent (Ra_eq), external and internal hazard indices (H_ex, H_in), and gamma index (I_γ) are also evaluated. All hazard parameter values were greater than the permissible and recommended limits and the average annual effective dose value exceeded the dose constraint (0.3 mSv y^-1). However, for occasionally exposed workers, the dose rate of 0.65 ± 0.02 mSv y^-1 is lower than recommended limit of 1 mSv y^-1 for public.

• 방사선산업학회지
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• 제17권1호
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• pp.33-44
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• 2023

The deep geological repository of high-level radioactive waste shall be designed to meet the safety objective set in the form of radiation dose or corresponding risk to protect human and the environment from radiation exposure. Engineering feasibility and conformity with the safety objective of the facility conceptual design can be demonstrated by comparing the assessment result using the computational model for scenario(s) describing the radionuclide release and transport from repository to biosphere system. In this study, as the preliminary study for developing the high-level radioactive waste disposal facility in Korea, we reviewed and analyzed the entire list of FEPs and how to handle each FEP from a general point of view, which are selected for the geosphere region in the radiological safety assessment performed for the license application of the KBS-3 type deep geological repository in Finland and Sweden. In Finland, five FEPs (i.e., stress redistribution, creep, stress redistribution, erosion and sedimentation in fractures, methane hydrate formation, and salt exclusion) were excluded or ignored in the radionuclide release and transport assessment. And, in Sweden, six FEPs (i.e., creep, surface weathering and erosion, erosion/sedimentation in fractures, methane hydrate formation, radiation effects (rock and grout), and earth current) were not considered for all time frames and earthquake out of a total of 25 FEPs for the geosphere. Based on these results, an FEP list (draft) for the geosphere was derived, and the relative importance of each item was evaluated for conducting the radiological safety assessment of the domestic deep geological disposal facility. Since most of information on the disposal facility in Korea has not been determined as of now, it is judged that all FEP items presented in Table 3 should be considered for the radiological safety assessment, and the relative importance derived from this study can be used in determining whether to apply each item in the future.

• Journal of Radiation Protection and Research
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• 제30권2호
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• pp.91-97
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• 2005

베이지안 기법은 객관적 자료 이외에 주관적 지식도 평가에 반영하는 특성으로 인해 최근 PRA에서 널리 사용되고 있다. 본 연구에서는 비파괴검사 장비 분실에 대한 방사선 위험도를 평가하기 위해 베이지안 기법을 활용하였다. U.S. NRC에서 제시한 선원분실 피폭 시나리오를 국내 실정에 맞게 재구성하였고 안전인자의 사고발생 확률에 국한하여 적용하였다. 사고발생 확률수정의 경우 Jeffreys사전분포를 사용한 결과가 모호사전분포를 사용한 결과보다 5 % 베이즈 하한치가 더 낮아서 방사선 사고와 같은 낮은 사고발생 확률을 가지는 시스템에 대한 위험도 평가에 적합하다. 위험도의 결과를 보면 일반인의 연간 예상되는 평균선량은 베이지안 기법이 고전적인 기법에 의거한 평가보다 높은 선량을 나타내는데 이는 수정된 안전인자 확률의 평균이 고전적 확률 참보다 높게 평가된 것에 기인한다. 국내의 경우 방사선 위험도 평가를 위한 자료구축이 미비한 바 베이지안 기법은 위험도 평가에 유용한 대안으로 활용할 수 있으며 이러한 연구는 위험도 정보-기반 규제에 기여할 것이다.

• 한국의학물리학회지:의학물리
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• 제33권4호
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• pp.53-62
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• 2022

In this study, we have investigated the shielding evaluation methodology for facilities using kV energy generators. We have collected and analysis of safety evaluation criteria and methodology for overseas facilities using radiation generators. And we investigated the current status of shielding evaluation of domestic industrial radiation generators. According to the statistical data from the Radiation Safety Information System, as of 2022, a total of 7,679 organizations are using radiation generating devices. Among them, 6,299 facilities use these devices for industrial purposes, which accounts for a considerable portion of radiation. The organizations that use these devices evaluate whether the exposure dose for workers and frequent visitors is suitable as per the limit regulated by the Nuclear Safety Act. Moreover, during this process, the safety shields are evaluated at the facilities that use the radiation generating devices. However, the facilities that use radiating devices having energy less than or equal to 6 MV for industrial purposes are still mostly evaluated and analyzed according to the National Council on Radiation Protection and Measurements 49 (NCRP 49) report published in 1976. We have investigated the technical standards of safety management, including the maximum permissible dose and parameters assessment criteria for facilities using radiation generating devices, based on the NCRP 49 and the American National Standards Institute/Health Physics Society N.43.3 reports, which are the representative reports related to radiation shielding management cases overseas.