• Nuclear Engineering and Technology
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• 제55권1호
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• pp.373-377
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• 2023

The Monte Carlo (MC) method has become an indispensable part of the nuclear radiation research field. Several widely used and well-known MC packages were developed for simulation of radiation transport and interaction with matter. All these MC packages require users to prepare an input script. The input script can become lengthy for complex models. The process of preparing these input scripts is time-consuming and error-prone. In the present work, we have developed an open-source GUI computer program for modelling radiation transport and interaction in multi-segmented slab phantoms using grid-based system for the widely used PHITS MC package. The developed tools would be useful for future users of PHITS MC package and particularly inexperienced users. The present program is distributed under GPL license and all users can freely download, modify and redistribute the program without any restrictions.

• 대한안전경영과학회:학술대회논문집
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• 대한안전경영과학회 2011년도 추계학술대회
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• pp.563-571
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• 2011

The purpose of the study was to evaluation of the radiation dose reduction using various automatic exposure control (AEC) systems in different manufactures multi-detector computed tomography (MDCT). We used three different manufacturers for the study: General Electric Healthcare, Philips Medical systems and Siemens Medical Solutions. The general scanning protocol was created for the each examination with the same scanning parameters as many as possible. In the various AEC systems, the evaluation of reduced-dose was evaluated by comparing to fixed mAs with using body phantom. Finally, when we applied to AEC for three manufacturers, the radiation dose reduction decreased each 35.3% in the GE, 58.2% in the Philips, and 48.6% in the Siemens. This applies to variety of the AEC systems which will be very useful to reduce the dose and to maintain the high quality.

• 의료법학
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• 제14권2호
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• pp.119-142
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• 2013

It is not easy to regulate the amount of radiation used for the medical purpose as there usually is more good than harm to the patient's health and life caused by the medical exposure to the radiation. However, the rapid increase of the use of diagnostic radiation involves a high possibility of increasing the radiation hazard exposure. Therefore, it is imperative to implement effective regulations in order to secure the safety of diagnostic radiation. The one and only rule we currently have for the diagnostic radiation is "Medicine Act" with only one clause dedicated to regulate the safety management that does not include any rules for the medical radiation. A set of inclusive rules for the whole medical radiation inclusive of diagnostic radiation and therapeutic radiation need to be based on the "Medicine Act" rather than "Nuclear Safety Act" in order to protect the medical professionals, patients and the guardians of patients from the hazards of diagnostic and/or therapeutic radiation that was not used the purpose of medical treatment. If there is an administrative measure to be imposed to secure the safety of diagnostic radiation, it is considered as exertion of governmental authority of administrative agency. There must be clear and realistic legal guidelines for in-fringe on people's interests. The administrative measures for the safety management of the diagnostic radiation must be clearly and specifically based on the law and the detailed standards for the administrative measures must be dele-gated by the presidential decree or departmental ordinance. Accordingly, the restrictions imposed by the administrative measures to the "Safety Inspection Institute of Radiation along with Radiation Exposure Measuring Institutes" should have clear legal basis as well and the detailed standards for the administrative measures should be regulated by the Ministry of Health and Welfare decree instead of the notification by the Director of Korean Centers for Disease Control and Prevention. While securing the safety of radiation on one side, careful review and up-grade on our legal system for the safety management of the diagnostic radiation is required on the other side to guarantee the legality, interest balance and reliability of the administrative measures.

• Journal of Radiation Protection and Research
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• 제37권4호
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• pp.219-225
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• 2012

방사선안전을 수행하는 방사선안전관리자를 대상으로 실제적인 방사선안전규제 수준을 파악하여 합리적인 안전규제 제도를 마련하는데 필요한 근거자료를 도출함으로써 방사선안전규제의 효율성과 편의성을 극대화할 수 있는 차별화된 규제에 도움이 되고자 하였다. IAEA의 RS-G-1.9 (2005), NRC의 NUREG Vol. 1~21 등과 국내 원자력안전법의 내용을 근거로 전체 약 10%에 해당되는 방사선이용기관의 방사선안전관리자를 대상으로 설문조사하였다. 피폭관리에 대한 요건($3.32{\pm}0.910$)이 가장 높은 인식수준을 나타냈고, 관련 서류의 기록, 비치, 보관에 대한 요건($2.84{\pm}0.826$)은 가장 낮은 인식수준을 나타냈다. 방사선원 현황 및 관리 요건, 시설 요건, 측정 및 오염관리 요건, 측정 장비 및 감시기 작동 요건, 교육 및 훈련 요건, 피폭관리 요건에서 산업기관이 의료기관보다 규제가 더 엄격해야 한다는 인식수준을 나타냈다. 방사선안전규제 수준이 산업기관과 의료기관에 통계적으로 유의한 차이가 있다는 것은 규제관련 그 원인이 존재하는 것이므로 실제적인 규제내용을 재평가해 볼 필요가 있음을 시사한다. 향후 연구에서는 국내 기관특성별로 규제요건을 개발하는 과정이 이루어질 필요가 있고, 기관특성을 고려하여 방사선안전규제를 수행한다면 편의성을 극대화한 안전규제를 달성할 수 있을 것이라고 사료된다.

• 한국의학물리학회지:의학물리
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• 제20권4호
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• pp.253-259
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• 2009

방사선관계종사자에 대한 개인피폭선량 측정의 정확성 및 신뢰성을 확보함으로써 방사선관계종사자의 건강을 보호하고 국민보건 수준향상에 기여하기 위한 개인피폭선량 측정기관의 선량측정 품질관리 기준을 국제기준에 적합하도록 개발할 필요성이 제기되고 있다. 국내 의료기관에서의 개인선량 관련법은 ANSI N13.11-1993 규정을 참조하고 있으나 미국을 비롯한 해외 여러 나라에서는 시험 범주를 줄이고 기준을 강화한 ANSI N13.11-2001을 이미 반영하여 개인피폭선량을 측정하고 있다. 제안하는 방법은 ANSI N13.11-2001을 참고하여 기준을 단순화하였고 유리선량계와 광자극선량계 같은 현재 법률에서 인정하지 않는 첨단기술을 이용하는 것을 막거나 방해할 수 있는 조치를 취하지 않으려고 하였다. 본 논문에서 제안하는 측정기관 품질관리기준은 개인피폭선량 성능시험기준은 관련법규개정에 참고할 수 있고, 측정기관 지도 감독에 활용할 수 있다.

• 대한안전경영과학회지
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• 제6권3호
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• pp.87-97
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• 2004

The National Health Insurance Act, the Industrial Health Act and the School Health Act require chest radiography at least once a year. In chest radiographic examination, most group examinations use indirect X-ray primarily aiming at diagnosing diseases and enhancing people's health. This study purposed to minimize radiation exposure dose by comparing it between direct and indirect chest X-ray studies. According to the result of comparing and analyzing radiation exposure dose, the average incident dose and penetrating dose were 0.929μGy and 0.179μGy respectively in direct chest X-ray and 6.807μGy and 1.337μGy in indirect chest X-ray In order to minimize radiation exposure dose at direct and indirect chest X-ray, indirect X-ray should be excluded from group examination if possible. Moreover, it is necessary to control the quality of equipment (Q/A & Q/C) systematically and to avoid using unqualified equipment in order to reduce radiation exposure dose.

• 대한디지털의료영상학회논문지
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• 제11권2호
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• pp.69-77
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• 2009

This study gives an account of the collateral standards in IEC 60601-1-3: 2008 specifying the general requirements for basic safety and essential performance of diagnostic X-ray equipment regarding radiation protection as it pertains to the production of X-rays. The collateral standards establish general requirements for safety regarding ionization radiation in diagnostic radiation systems and describe a verifiable evaluation method of suitable requirements regarding control over the lowest possible dose equivalent for patients, radiologic technologists, and others. The particular standards for each equipment can be determined by the general requirements in the collateral standard and the particular standard is followed in the risk management file. The guidelines for radiation safety of diagnostic radiation systems is written up in ISO 13485, ISO 14971, IEC 60601-1-3(2002)1st edition, medical electric equipment part 1-3, and the general requirements for safety-collateral standards: programmable electrical medical systems. Therefore the diagnostic radiation system protects citizens' health rights with the establishment and revisions of laws and standards for diagnostic radiation systems as a background for the general requirements of radiation safe guards applies, as an international trend, standards regarding the medical radiation safety management. The diagnostic radiation system will also assure competitive power through a conforming evaluation unifying the differing standards, technical specifications, and recognized processes.

• Nuclear Engineering and Technology
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• 제54권2호
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• pp.449-455
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• 2022

The rapid rise in the application of novel treatment techniques, such as intensity-modulated radiotherapy (IMRT), motivated us to survey the status of Korea's radiation safety management and the shielding designs of facilities employing medical linear accelerators (LINACs). To this end, a questionnaire was used to collect information on LINAC facilities and treatments, workload, shielding design, shielding management, and path of obtaining shielding information. Out of 100 domestic institutions, 52 responded to the survey. Approximately 70% of the institutions utilized IMRT for more than 60% of their cases, and an IMRT factor of 5 was adopted by 75% of these institutions. Over 80% of the institutions accounted for the applied time-averaged dose rate per week and instantaneous dose equivalent rates in their shielding designs. Approximately 45% of the institutions obtained important shielding information via a radiation shielding design company and the NCRP-151 report. Overall, most facilities were shown to follow the standards recommended by the relevant international agencies. However, the requirement to establish standardized shielding design information and clarify ambiguous paths for information acquisition was also highlighted. Therefore, the study's results can be used as a foundation for establishing a safety control system and for creating adequate shielding designs.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1210-1217
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• 2023

The assessment of radiation fields in the lithium loop pipes and dump tank during the operation were performed for International Fusion Materials Irradiation Facility - DEMO-Oriented NEutron Source (IFMIF-DONES) in order to obtain the radiation dose-rate maps in the component surroundings. Variance reduction techniques such as weight window mesh (produced with the ADVANTG code) were applied to bring the statistical uncertainty down to a reasonable level. The biological dose was given in the study, and potential shielding optimization is suggested and more thoroughly evaluated. The MCNP Monte Carlo was used to simulate a gamma particle transport for radiation shielding purposes for the current Li Systems' design. In addition, the shielding efficiency was identified for the Impurity Control System components and the dump tank. The analysis reported in this paper takes into account the radiation decay source from and activated corrosion products (ACPs), which is created by d-Li interaction. As a consequence, the radiation (resulting from ACPs and Be-7) shielding calculations have been carried out for safety considerations.

• 한국안전학회지
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• 제31권5호
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• pp.22-27
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• 2016

The Electrostatic Charge Prevention Technology is a core factor that highly influences the yield of Ultra High Resolution Flat Panel Display and high-integrated semiconductor manufacturing processes. The corona or x-ray ionizations are commonly used in order to eliminate static charges during manufacturing processes. To develop such a revolutionary x-ray ionizer that is free of x-ray radiation and has function to control the volume of ion formation simultaneously is a goal of this research and it absolutely overcomes the current risks of x-ray ionization. Under the International Commission on Radiological Protection, it must have a leakage radiation level that should be lower than a recommended level that is $1{\mu}Sv/hour$. In this research, the new generation of x-ray ionizer can easily control both the volume of ion formation and the leakage radiation level at the same time. In the research, the test constraints were set and the descriptions are as below; First, In order not to leak x-ray radiation while testing, the shielding box was fully installed around the test equipment area. Second, Implement the metallic Ring Electrode along a tube window and applied zero to ${\pm}8kV$ with respect to manage the positive and negative ions formation. Lastly, the ion duty ratio was able to be controlled in different test set-ups along with a free x-ray leakage through the metallic Ring Electrode. In the result of experiment, the maximum x-ray radiation leakage was $0.2{\mu}Sv/h$. These outcome is lower than the ICRP 103 recommended value, which is $1{\mu}Sv/h$. When applying voltage to the metallic ring electrode, the positive decay time was 2.18s at the distance of 300 mm and its slope was 0.272. In addition, the negative decay time was 2.1s at the distance of 300 mm and its slope was 0.262. At the distance of 200 mm, the positive decay time was 2.29s and its slope was 0.286. The negative decay time was 2.35s and its slope was 0.293. At the distance of 100 mm, the positive decay time was 2.71s and its slope was 0.338. The negative decay time was 3.07s and its slope was 0.383. According to these research, the observation was shown that these new concept of ionizer is able to minimize the leakage radiation level and to control the positive and negative ion duty ratio while ionization.