• 한국방사선학회논문지
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• 제6권2호
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• pp.115-120
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• 2012

레이저 기술의 발전과 더불어 다양한 의료영역에서 레이저가 사용되고 있으며 그로 인한 위험성도 증가하고 있다. 레이저를 안전하게 사용하기 위해서는 레이저의 안전에 관한 지식을 가지고 관리할 수 있는 사람이 지정될 필요가 있다. 이에 따라 많은 나라에서 레이저안전관리자 체제를 운영하고 있다. 의료레이저안전관리자는 레이저의 안전사용과 관련하여 교육과 훈련 등의 권한과 책임을 가진다. 본 연구에서는 의료레이저안전관리자의 미국의 운영현황을 살펴보고 의료레이저안전관리자의 역할과 국내 도입 방안을 살펴보았다.

• 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.

• 방사선산업학회지
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• 제17권1호
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• pp.45-59
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• 2023

The transport calculation for a wide variety of radionuclides contained in high-level radioactive waste, especially spent nuclear fuel, is computationally difficult, and input data collection for this also take a considerable amount of time. Accordingly, considering limited resources, it is possible to reduce the calculation time while minimizing impact on accuracy by including only radionuclides important to calculation result through applying some criteria among potential radiation source terms that may release into environment. In this paper, therefore, we reviewed and analyzed the screening process performed to select radionuclides to be considered in the safety assessment for the KBS-3 type repository in Sweden and Finland. In both countries, it was confirmed that a list of radionuclides was selected by comprehensively considering screening criteria such as radioactivity inventory, half-life, radiotoxicity, risk quotient, and transport properties, and etc. A comparison of radionuclides included in the radiological safety assessment in both countries suggests that most of nuclides are considered in common, and a few nuclides considered only in one country are due to differences in decay chain treatment or spent fuel types. As of now, since most of information on the disposal facility in Korea has not been determined, it is necessary to comprehensively model release and transport of all radionuclides considered in Sweden and Finland when performing the radiological safety assessment. Based on these results, we derived the screening concept of selecting a list of radionuclides to be considered in the radiological safety assessment for the domestic KBS-3 type geological disposal facility, and this result is expected to be used as technical basis for confirming conformity with the safety objective. In a more detailed evaluation reflecting domestic characteristics in the future, it would be desirable to consider only radionuclides selected in accordance with the screening procedure. However, further research should be conducted to determine the quantitative limit for each criteria.

• 대한방사선기술학회지:방사선기술과학
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• 제43권2호
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• pp.123-128
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• 2020

Radiation Following the 2011 Fukushima nuclear accident in Japan, public interest and anxiety about radiation safety increased, and vague anxiety about commonly exposed living radiation was generated. The Atomic Energy Safety Commission has been conducting a survey of processed products that advertise "negative ions" and "far-infrared" emissions under the Living Radiation Safety Management Act. In this study, in-depth analysis was performed from a statistical point of view using the measurement data presented in the Nuclear Safety Committee's actual survey analysis report as secondary data. As a result, there was a statistically significant difference (p<0.005) between latex and civil affairs products. There were also statistically significant differences (p<0.05) in the results of testing whether there were significant differences in the annual exposure dose between groups after categorizing 71 civil products, including radon beds, into bed, bedding, and living and other categories. The correlation analysis results also confirm that, as is commonly known, the annual doses received from processed products are associated with radon derived from U-238 and Th-232.

• 대한방사선협회지
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• 제27권2호
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• pp.260-268
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• 2001

Ⅰ. Introduction : 'The regulation for the safety management of diagnostic radiation apparatus' legislated and it has been managed systematially. So that, it enables a national health to be protected from harmful radiation. But, managers and administers of

• Nuclear Engineering and Technology
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• 제56권9호
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• pp.3483-3490
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• 2024

The initial size distribution and morphological parameters of sodium aerosols are critical in evaluating the accidental suspended aerosol behaviour in Sodium-cooled Fast Reactor (SFR) containment. Mass-based measurements were more familiar in characterizing the sodium aerosols. Real-time number size distribution measurements are carried out in this study. The sensitivity analysis of sodium aerosol effective density (ρ_e) in deriving the actual number size distributions from the measured Aerodynamic Particle Size Distributions (APSD) and predicting suspended aerosol dynamics is presented. Tests are conducted in a 1 m³ chamber at 47 ± 3% RH for different initial mass concentrations (M₀) of 0.1, 1, and 2.9 g/m³. The initial APSDs measured just after the generation completions are observed to be polydisperse with the count median aerodynamic diameter (CMAD) < 1 ㎛. The literature reported ρ_e values of sodium aerosols, 2.27, 1.362, and 0.61 g/cm³ are used to derive mobility equivalent PSDs from APSD in each test. The real-time number concentration decay and size growth for four different PSDs are measured and compared with the estimate using nodal method-based code to ascertain the actual parameters. The validated parameters CMD = 0.66 ㎛, σ_g = 1.96, ρ_e = 1 g/cm³ and χ = 1 are used for improved estimation of sodium aerosol dynamics in Indian SFR containment with M₀ = 4 g/m³ for severe accident scenarios.

• 한국안전학회지
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• 제27권6호
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• pp.192-204
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• 2012

For a severe accident of nuclear power plant, an approach to estimation of the radiological source term using a severe accident code(MELCOR) has been proposed. Although the MELCOR code has a capability to estimate the radiological source term, it has been hardly utilized for the radiological consequence analysis mainly due to a lack of understanding on the relevant function employed in MELCOR and severe accident phenomena. In order to estimate the severe accident source term to be linked with the radiological consequence analysis, this study proposes 4-step procedure: (1) selection of plant condition leading to a severe accident(i.e., accident sequence), (2) analysis of the relevant severe accident code, (3) investigation of the code analysis results and post-processing, and (4) generation of radiological source term information for the consequence analysis. The feasibility study of the present approach to an early containment failure sequence caused by a fast station blackout(SBO) of a reference plant (OPR-1000), showed that while the MELCOR code has an integrated capability for severe accident and source term analysis, it has a large degree of uncertainty in quantifying the radiological source term. Key insights obtained from the present study were: (1) key parameters employed in a typical code for the consequence analysis(i.e., MACCS) could be generated by MELCOR code; (2) the MELOCR code simulation for an assessment of the selected accident sequence has a large degree of uncertainty in determining the accident scenario and severe accident phenomena; and (3) the generation of source term information for the consequence analysis relies on an expert opinion in both areas of severe accident analysis and consequence analysis. Nevertheless, the MELCOR code had a great advantage in estimating the radiological source term such as reflection of the current state of art in the area of severe accident and radiological source term.

• 한국재난정보학회 논문집
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• 제20권3호
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• pp.573-583
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• 2024

연구목적:본 연구는 통풍형 간이 화생방 방호시설 표준 평면을 공간 대상으로 하여 기존 보완 전의 시설 조건을 기준으로 화생방 공격 시 기지 내의 화생방 방호시설의 화생방 물질 유동을 예측하고 오염물질 흐름 및 독성물질에 의한 인체 영향을 분석하고 누기 발생을 파악하였다. 연구방법:건물의 특성을 반영한 보완 공사가 이루어진 간이 화생방 방호시설 개선 평면 시설기준으로 개선되었을 때를 가정하여 동일한 조건의 화생방 공격 시에 기지 내의 화생방 방호시설의 화생방 물질의 유동을 예측하고 오염물질의 흐름 및 독성물질에 의한 재실자의 영향을 분석하며 공간 안전성을 파악하였다. 연구결과: 1안의 경우 기존 평면 간이 화생방 방호시설 미설치 공간에서는 약 250초 이후에 누기가 발생하는 것으로 나타났다. 2안과 3안의 경우 기존평면 간이 화생방 방호시설 미설치 공간에서는 누기가 발생하는 것으로 나타났다. 결론: 1안 ,2안, 3안의 경우 개선된 평면에서는 누기 발생이 발생하지 않아 기밀성이 유지되는 것으로 나타났다. 4안의 경우 기존평면 간이 화생방 방호시설 미설치 공간에서는 누기 발생으로 인한 기밀성 유지가 되지 않았다.

• 대한방사선기술학회지:방사선기술과학
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• 제44권5호
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• pp.545-554
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• 2021

According to the changes of the medical environment of the times, it is necessary to discuss the issues of the doctor's medical guidance and to conduct continuous research so that alternatives can be prepared systematically. Furthermore, in order to enhance the professionalism of radiological technologists and to develop the medical technician system, the new Radiological Technologist Independent Act has been established, which contains the overall contents of the scope of work, professional qualifications, and specialized education of radiological technologists, and provides quality medical services to patients through professional procedures and treatment. In order to increase the level of medical care, the purpose, definition, mission, role, and scope of work specified in the Medical Act, Medical Service Technologists, etc. Act, the Enforcement Decree, and the Enforcement Rules were variously analyzed and new directions were presented. First, the definition of a medical technician should use a generic term so that the factors of conflict and prejudice could be resolved. Second, change the doctor's guide to doctor's prescription; and then legislate the authority to sign and write medical records after examination by radiological technologists, thereby prohibiting unlicensed technicians that seriously endanger patient safety. Third, an accurate definition of radiological technologists' roles should be established; not only selection and management of radiological technologists' work but also procedures and treatment for each radiology field should be specified to suit the current medical system. Fourth, a professional radiological technologists' qualification system and a specialized education system should be established in order to secure human resources that could provide patients trust in procedures and treatment based on professional knowledge and experience in the field of radiology. Fifth, the Education and Evaluation Institute should be operated in Korea education system to educate the professional knowledge and competency for students. In addition, it is necessary to in-depth analysis of foreign cases could be applied to the medical system and education system in Korea; it could strive to nurture systematic human resources.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.387-388
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• 2019