• 대한방사선기술학회지:방사선기술과학
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• 제33권4호
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• pp.341-348
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• 2010

상 하지 촬영 시 서울 경기지역 병원의 FPD(Flat Pannel Detector) System 사용 실태와 격자 사용에 따른 환자 선량 및 C-D Phantom에 의한 화질평가, 임상 평가자들에 의한 영상평가를 한 결과 다음과 같은 결론을 얻었다. 1. FPD system(12대)의 사용 실태 조사결과 격자비는 8 : 1에서 13 : 1까지이며, 12 : 1이 6대로 가장 많았다. 이 중 격자의 탈 부착이 가능한 장비는 8대이지만, 사용하지 않는 것이 5대(62.5%)로 격자를 그대로 사용하는 곳이 9곳(75.5%)이었다. 2. 실험에 사용된 장비에서 격자사용으로 환자가 받은 선량이 4.13배에서 4.79배까지 많이 받는 것으로 나타났다. 3. 노출조건(mAs)의 변화(0.5배나 2.0배)에 따라 환자가 받는 선량의 차이는 환자 두께에 따라 크게 차이 나지는 않았다. 4. C-D Phantom에 따른 영상의 화질평가는 격자 사용 시와 노출량이 많아질 때 영상의 식별은 잘 되었다. 5. 임상 평가는 두께가 얇은 Hand PA 영상에서는 격자사용을 하지 않는 것이 더 좋았다. 두께가 두꺼운 Knee AP 영상에서는 격자를 사용하는 것이 좋다는 평가를 받았다. 그러나 환자선량이 적어진다면 격자를 사용하지 않겠다는 의견이 5명 중 3명으로 더 많았다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(4)
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• pp.51-56
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• 1996

In a NNP (Nuclear Power Plant) severe accident, radionuclides are dispersed into the air. The official regulatory institute, KINS (Korea Institute of Nuclear Safety), has been authorized and developing Computerized technical Advisory system for the Radiological Emergency preparedness (CARE). In this paper, in line with the CARE system, we presented the result of a modularized intermediate-level emergency dose assessment computer code. The RADCON (RADiological CONsequence analysis) version 3.0, which is operable on PC, is developed for simulating emergency situation by considering continuous washout phenomena, and provide a function of effective emergency planning. The source files are coded by using C language in order to increase the compatibility with the other computer system and modularized to adjust the functions and characteristics of each module fer easy understanding and further modification.

• 한국의학물리학회지:의학물리
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• 제28권2호
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• pp.45-48
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• 2017

This paper evaluated the amount of radiation generated by wedge filters during radiation therapy using a high-energy linear accelerator, and the dose to the worker during wedge replacement. After 10-MV photon beam was irradiated with wedge filter, the wedge was removed from the linear accelerator, and the dose rate and energy spectrum were measured. The initial measurement was approximately 1 uSv/h, and the radiation level was reduced to 0.3 uSv/h after 6 min. The effective half-life derived from the dose rate measurement was approximately 3.5 min, and the influence of AI-28 was about 53%. From the energy spectrum measurements, a peak of 1,799 keV was measured for AI-28, while the peak for Co-58 was not measured in the control room. The peaks for Au-106 and Cd-105 were found only measurement was done without wedge removement from the linear accelerator. The additional doses received by the radiation worker during wedge replacement were estimated to be 0.08-0.4 mSv per year.

• 방사선산업학회지
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• 제18권3호
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• pp.195-207
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• 2024

International organizations such as IAEA and EC recommend graded approach by identifying NORM industries requiring radiation protection. In Korea, single regulation rather than graded regulation for NORM industry is applied. Therefore, it consumes more manpower and costs than necessary for both regulators and workers, and is not optimized. The purpose of this study is to analyze domestic and foreign NORM industry regulatory standards and radiological characteristics for graded approach of NORM industry in Korea. Safety reports and publications such as SRS 49 and ICRP 142 published by international organizations were investigated, and domestic and foreign NORM regulatory guidelines and legislation such as Health Canada and the Act on Protective Action Guidelines Against Radiation in the Natural Environment were investigated to indicate NORM industries and regulatory standards. The radioactivity concentration of raw materials or by-products, radiation dose by industrial process of the NORM industry identified in IAEA and Korea were investigated. Nine NORM industries in Korea were identified based on the NORM industry from IAEA and KINS survey report. Foreign countries such as Canada, UK and Denmark were executing graded approach such as classification of dose level or licensing, registration, notification based on safety assessment. Radioactivity concentration of domestic and foreign NORM industries were widespread up to 200 Bq g^-1 or higher based on industrial process and work type, and numerous NORM industries that exceeded radiation dose of 1 mSv y^-1 were indicated. Therefore, it is necessary to consider handling materials and work types of identified NORM industry when establishing graded approach for NORM industry in Korea considering domestic situation. The results of this study are expected to be used as basic data for developing methodology of graded approach for NORM industry in Korea.

• Nuclear Engineering and Technology
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• 제49권2호
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• pp.411-425
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• 2017

Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircraft impact is discussed through a numerical structural analysis and an analytical fragility assessment. Sequences of the impact scenario are shown in a developed event tree, with uncertainties considered in the impact analysis and failure probabilities calculated. To evaluate the influence of parameters relevant to design safety, risks are estimated for three specification levels of cask and storage facility structures. The proposed assessment procedure includes the determination of the loading parameters, reference impact scenario, structural response analyses of facility walls, cask containment, and fuel assemblies, and a radiological consequence analysis with dose-risk estimation. The risk results for the proposed scenario in this study are expected to be small relative to those of design basis accidents for best-estimated conservative values. The importance of this framework is seen in its flexibility to evaluate the capability of the facility to withstand an aircraft impact and in its ability to anticipate potential realistic risks; the framework also provides insight into epistemic uncertainty in the available data and into the sensitivity of the design parameters for future research.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.368-372
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• 2016

Background: Methodologies for a series of radiological consequence assessments show a distinctive difference according to the design principles of the original nuclear suppliers and their technical standards to be imposed. This is due to the uncertainties of the accidental source term, radionuclide behavior in the environment, and subsequent radiological dose. Both types of PWR and PHWR are operated in Korea. However, technical standards for evaluating atmospheric dispersion have been enacted based on the U.S. NRC's positions regardless of the reactor types. For this reason, it might cause a controversy between the licensor and licensee of a nuclear power plant. Materials and Methods: It was modelled under the framework of the NRC Regulatory Guide 1.145 for light-water reactors, reflecting the features of heavy-water reactors as specified in the Canadian National Standard and the modelling features in MACCS2, such as atmospheric diffusion coefficient, ground deposition, surface roughness, radioactive plume depletion, and exposure from ground deposition. Results and Discussion: An integrated accident consequence assessment code, ACCESS (Accident Consequence Assessment Code for Evaluating Site Suitability), was developed by taking into account the unique regulatory positions for reactor types under the framework of the current Korean technical standards. Field tracer experiments and hand calculations have been carried out for validation and verification of the models. Conclusion: The modelling approaches of ACCESS and its features are introduced, and its applicative results for a hypothetical accidental scenario are comprehensively discussed. In an applicative study, the predicted results by the light-water reactor assessment model were higher than those by other models in terms of total doses.

• 한국방사선학회논문지
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• 제14권2호
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• pp.169-178
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• 2020

국민의 의료수준 향상으로 CT 검사건수는 매년 증가되고 있는 추세이며, 이에 따라 연간 의료 방사선에 의한 피폭선량 또한 증가되고 있다. 이에 본 연구에서는 CT 부위별 검사 시 노출되는 인체의 유효선량을 평가하고, 이로 인한 생애 암 귀속 위험도를 추정하고자 한다. 첫 번째로, CT 진단참고수준 가이드라인에서 제시하는 부위 중 5가지를 선정하였으며, CT 장치를 통해 각 검사 부위별로 노출되는 인체의 유효선량을 평가하였다. 두 번째로, 동일한 조건 내 ALARA-CT 프로그램을 이용하여 인체 장기 및 유효선량을 산정하였으며, 국내 DRL 수준과 비교하여 검사 프로토콜에 대한 적정성을 평가하였다. 세 번째로, CT 검사 시 노출되는 유효선량에 의한 생애 암 귀속 위험도(LAR)을 추정하였다. 그 결과, 검사 중 복부 다중시기 검사 시 21.18 mSv로 가장 높은 유효선량을 나타내었으며, 복부검사를 제외한 나머지 검사에서는 DRL 이하의 선량수준을 나타내었다. 동일한 조건 내 선량계산 프로그램을 이용한 유효선량 평가 결과, 각 검사별로 약 1.1 ~ 1.9배 이상 높은 결과를 나타내었으며, 장기선량의 경우 검사 부위에 근접한 장기일수록 산란선에 의해 높은 영향을 나타내었다. CT 검사 시 성인의 생애 암 귀속 위험도의 경우, 연령이 증가함에 따라 점차적으로 감소되는 양상을 보였으며, 성별에 따라 다소 상이한 결과를 나타내었다.

• 방사선산업학회지
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• 제17권2호
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• pp.151-160
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• 2023

The International Atomic Energy Agency (IAEA) proposes 11 industries that handle Naturally Occurring Radioactive Material (NORM) that are considered to need management. A water treatment facility is one of the above industries that takes in groundwater and produces drinking water through a water treatment process. Groundwater can accumulate natural radionuclides such as uranium and thorium in raw water by contacting rocks or soil containing natural radionuclides. Therefore, there is a possibility that workers in water treatment facilities will be exposed due to the accumulation of natural radionuclides in the water treatment process. The goal of this study is to evaluate the external radiation dose according to the working type of workers in water treatment facilities. In order to achieve the above goal, the study was conducted by dividing it into 1) analysis of the exposure environment, 2) measurement of the external radiation dose rate 3) evaluation of the external radiation dose. In the stage of analyzing the exposure environment, major processes that are expected to occur significantly were derived. In the measurement stage of the external radiation dose rate, a map of the external radiation dose rate was prepared by measuring the spatial radiation dose rate in major processes. Through this, detailed measurement points were selected considering the movement of workers. In the external radiation dose evaluation stage, the external radiation dose was evaluated based on the previously derived external radiation dose rate and working time. As a result of measuring the external radiation dose rate at the detailed points of water treatment facilities A to C, it was 1.90×10^-1 to 3.75×10⁰ μSv h^-1, and the external radiation dose was analyzed as 3.27×10^-3 to 9.85×10^-2 mSv y^-1. The maximum external radiation dose appeared during the disinfection and cleaning of activated carbon at facility B, and it is judged that natural radionuclides were concentrated in activated carbon. It was found that the external radiation dose of workers in the water treatment facility was less than 1mSv y^-1, which is about 10% of the dose limit for the public. As a result of this study, it was found that the radiological effect of external radiation dose of domestic water treatment facility workers was insignificant. The results are expected to contribute as background data to present optimized safety management measures for domestic NORM industries in the future.

• Journal of Radiation Protection and Research
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• 제46권2호
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• pp.80-82
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• 2021

Dr. Haruyuki Ogino, a member of the Japan Health Physics Society (JHPS), was awarded the 2021 Bo Lindell Medal by the International Commission on Radiological Protection (ICRP). To commemorate this, the "Joint JHPS-KARP-ARPS program for young radiation protection (RP) scientists to discuss the future of RP" was organized via a web meeting system. First, Dr. Ogino gave a lecture, and then young researchers selected from each academic society made presentations on the future of RP. After the presentations by the three researchers, a free talk was held-young researcher groups of each country being active is a great opportunity to collaborate and exchange information. It was emphasized that the low awareness of knowledge related to radiation has been common to all of the participating countries. Thus, it is necessary to utilize communication via web technology, as done for this program, effectively. One of the biggest advantages for Asia and Oceania is that we do not have a significant time difference. The round-table discussion was concluded by expressing the hope of active exchange and development of young researchers in the future.

• Journal of Radiation Protection and Research
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• 제32권1호
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• pp.1-8
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• 2007

도시지역의 방사능 오염으로 거주민의 피폭영향을 평가할 수 있는 모델 METRO-K를 개발하였다. 모델의 특성으로 1) 실험 또는 경험자료를 사용하기 때문에 수학식이 간단하여 이해가 쉬울 뿐 아니라 계산에 필요한 변수의 수가 적으며 2) 도시환경을 구성하는 5가지 기본표면 만을 사용하여 복잡하고 다양한 주변 환경을 쉽게 구성할 수 있으며 3) 각기 다른 오염 표면으로 인한 선량을 평가함으로써 표면마다 적합한 제염대책을 수립하는데 용이하다. 피폭자의 특정 위치에서 각기 다른 오염표면으로부터 받게 되는 선량은 감마에너지와 오염 표면별 공기커마 값을 데이터 라이브러리로 만들어 평가에 이용하였다. 유럽 도시지 역의 4가지 대표적 거주형태 에 대한 공기커마 값을 사용하여 우리나라 도시지역의 7가지 대표적 주거형태에 적합하도록 공기커마 값을 조합하여 적용하였다. 장기간 방사성물질의 누설을 고려하여 하루 단위의 핵종별 공기중 농도, 강우량, 핵종의 화학적 형태 구성분율이 입력되면 침적 후 시간에 따른 각기 다른 표면에서의 공기중 흡수선량률과 피폭자의 거주 위치에 따른 인체 선량률이 평가된다. 아파트 밀집지역에 대한 가상 오염 시나리오의 적용결과 피폭자의 거주위치 뿐 아니라 피폭자가 거주하는 주변 환경에 따라 인체 선량률은 확연한 차이를 나타냈다.