• 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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• 제13권2호
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• pp.67-77
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• 1988

원자력발전소의 비상사태 발생시 효과적인 비상대책 수립을 위하여 인근 주민에 대한 신속한 피폭선량 평가 시스템의 개발이 강조되고 있다. 여기서 개발한 시스템은 다양한 원전의 사고에 대해 인근 주민에 대한 방사선 영향의 신속한 평가 모델로서 마이크로 컴퓨터에 기초한 프로그램이며, 문답형의 메뉴방식의 사용자 입력구조를 가지고 있고 수행 결과의 출력은 표 또는 그래픽 형식의 구조를 가지고 있어서 신속한 피폭선량평가 수행뿐만 아니라 신속한 결과 판독이 가능하여 비상대책 활동을 위한 결정에 도움을 준다.

• 방사성폐기물학회지
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• 제17권1호
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• pp.95-106
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• 2019

원전 해체를 준비함에 있어 정성적 또는 정량적 위험도 평가는 필수요소이다. 해체 공정간 발생하는 방사선학적 및 비방사선학적 위험요소는 해체 작업자 및 대중의 안전을 보장하기 위해 사전에 평가되어야 한다. 현재 해체 경험이 많은 미국의 기존 사업자들 및 NRC의 경우 위험의 중대성만 평가하는 결정론적 위험도 평가에 집중하고 있다. 하지만 최근 IAEA는 위험도 매트릭스를 활용한 위험도평가를 결정론적 위험도 평가의 대체안으로 제안하고 있다. 따라서 본 연구에서는 위험도평가에 앞서 해체 공정 별 해체 활동을 Risk Breakdown Structure에 맞추어 정리하였고, 미국 20여개 해체 원전에서 해체 공정별 위험도 평가 시행 중 선정한 해체 활동간 잠재적 사고를 해체 활동에 맞게 체계적으로 정리하였다. 그리고 복합 리스크 매트릭스를 개발 및 활용하여 해체 공정간 방사선학적 및 비방사선학적 위험요소의 위험도를 평가하여 정량적으로 수치화 하였다.

• 대한방사선방어학회:학술대회논문집
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• 대한방사선방어학회 2010년도 춘계 학술발표회 및 심포지엄
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• pp.100-101
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• 2010

• 대한방사선기술학회지:방사선기술과학
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• 제44권1호
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• pp.31-37
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• 2021

This study aim of quantitative assessment of Noise Power Spectrum(NPS) and image characteristics of by acquired the optimal image for noise characteristics and quality assurance by using magnetic resonance imaging(MRI). MRI device was (MAGNETOM Vida 3.0T MRI; Siemense healthcare system; Germany) used and the head/neck shim MR receive coil were 20 channels coil and a diameter 200 mm hemisphere phantom. Frequency signal could be acquired the K-space trajectory image and white image for NPS. The T2 image highest quantitatively value for NPS finding of showed the best value of 0.026 based on the T2 frequency of 1.0 mm-1. The NPS acquired of showed that the T1 CE turbo image was 0.077, the T1 CE Conca2 turbo image was 0.056, T1 turbo image was 0.061, and the T1 Conca2 turbo image was 0.066. The assessment of NPS image characteristics of this study were to that could be used efficiently of the MRI and to present the quantitative evaluation methods and image noise characteristics of 3.0T MRI.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.238-247
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• 2023

The present work represents a technical guideline for decommissioning a disused teletherapy machine model Theratron-780 and contains category one ⁶⁰Co radioactive source. The first section predicts the dose rate from the source in case of normal and radiological emergency situations via FLUKA-MC simulation code. Moreover, the dose assessment for the occupational during the whole process is calculated and compared to the measured values. A suggested cordoned area for safety and security in a radiological emergency is simulated. The second section lists the whole process's technical procedures, including (preview, dismantle, securing, transport and storage) of the disused teletherapy machine. Results show that the maximum obtained accumulated dose for occupational were found to be 24.5 ± 4.9 μSv in the dismantle and securing process in addition to 3.5 ± 1.8 μSv during loading on the transport vehicle and unloading at the storage facility. It was found that the measured accumulated dose for workers is in good agreement with the estimated one by uncertainty not exceeding 5% in normal operating conditions.

• 대한방사선기술학회지:방사선기술과학
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• 제22권1호
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• pp.79-85
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• 1999

This is an exploratory study to describe clinical demonstration patterns assessment and training-related problems(TRP) in Korea. A probability sample was drawn from Nation-Wide area by a multi-stage cluster sampling. This study in radiotechnological students of college over two years from 1997. Clinical demonstration patterns in this study involve a fundamental concept of radiotechnological students, a general notion of clinical demonstration, a rates of satisfaction in clinical demonstration, clinical demonstration patterns assessment, and training-related problems(TRP). High prevalence rates of clinical demonstration were found in male, students over twenty-four years old, those who perform at least hospital in college of medicine.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.424-435
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• 2016

Background: The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. Materials and Methods: The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. Results and Discussion: A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. Conclusion: The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.

• Journal of Yeungnam Medical Science
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• 제36권1호
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• pp.54-58
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• 2019

Adrenocortical carcinoma is a rare type of endocrine malignancy with an annual incidence of approximately 1-2 cases per million. The majority of these tumors secrete cortisol, and a few secrete aldosterone or androgen. Estrogen-secreting adrenocortical carcinomas are extremely rare, irrespective of the secretion status of other adrenocortical hormones. Here, we report the case of a 53-year-old man with a cortisol and estrogen-secreting adrenocortical carcinoma. The patient presented with gynecomastia and abdominal discomfort. Radiological assessment revealed a tumor measuring $21{\times}15.3{\times}12cm$ localized to the retroperitoneum. A hormonal evaluation revealed increased levels of estradiol, dehydroepiandrosterone sulfate, and cortisol. The patient underwent a right adrenalectomy, and the pathological examination revealed an adrenocortical carcinoma with a Weiss' score of 6. After surgery, he was treated with adjuvant radiotherapy. Twenty-one months after treatment, the patient remains alive with no evidence of recurrence.

• 방사성폐기물학회지
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• 제12권2호
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• pp.171-178
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• 2014

원전 해체 시 원자력설비는 안전하게 해체되어야 한다. 고리 1호기나 월성 1호기와 같은 노후화된 원전의 경우 곧 원전 해체를 계획하고 있는 대상 원전이지만, 이 원전들의 가동 중단 후 해체 시 선원항 평가 기준, 제염 및 해체 기술 등의 독자적인 국내 기술 확보는 미흡한 실정이다. 본 연구의 목적은 원전 선원항 평가 기술 중 하나로 In-Situ 기법을 이용하여 대형 원전 기기를 직접 측정하여 측정대상체에 대한 선원항 평가방법을 개발하는 것이다. 원자로 헤드를 별도의 해체 없이 이동형 감마핵종분석기를 이용하여 직접 측정법으로 분석하고 간접 측정을 병행하여 측정 결과를 보완하였다. 그리고, 표면오염시료는 방사화학분석을 수행하였다. 분석 결과를 확장하여 원자로의 핵종 재고량을 계산하였다. 본 연구 결과를 토대로 각 핵종별 방사능량 변화에 따라 해체 시점을 결정할 수 있으며, 원전 해체 시 작업자의 피폭 저감에 도움이 될 것으로 기대한다.