• Journal of Radiation Protection and Research
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• 제47권1호
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• pp.50-57
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• 2022

Background: There are several proton therapy facilities in operation or planned in Taiwan, and these facilities are anticipated to not only treat cancer but also provide beam services to the industry or academia. The simplified approach based on the Monte Carlo-based data sets (source terms and attenuation lengths) with the point-source line-of-sight approximation is friendly in the design stage of the proton therapy facilities because it is intuitive and easy to use. The purpose of this study is to expand the Monte Carlo-based data sets to allow the simplified approach to cover the application of proton beams more widely. Materials and Methods: In this work, the MCNP6 Monte Carlo code was used in three simulations to achieve the purpose, including the neutron yield calculation, Monte Carlo-based data sets generation, and dose assessment in simple cases to demonstrate the effectiveness of the generated data sets. Results and Discussion: The consistent comparison of the simplified approach and Monte Carlo simulation results show the effectiveness and advantage of applying the data set to a quick shielding design and conservative dose assessment for proton therapy facilities. Conclusion: This study has expanded the existing Monte Carlo-based data set to allow the simplified approach method to be used for dose assessment or shielding design for beam services in proton therapy facilities. It should be noted that the default model of the MCNP6 is no longer the Bertini model but the CEM (cascade-exciton model), therefore, the results of the simplified approach will be more conservative when it was used to do the double confirmation of the final shielding design.

• Nuclear Engineering and Technology
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• 제44권7호
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• pp.825-830
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• 2012

Radiation and its various industrial applications have been growing at approximately 10 percent per year for the past decade in Korea. As a result, the importance of the Education and Training (E&T) in radiation protection is of upmost importance. This paper is intended to investigate the present status of the E&T on radiation protection and safety in Korea and to draw up the improvements of the E&T courses required for building the national radiation safety infrastructure. For these purposes, the E&T data from the six major domestic organizations providing radiation protection training courses were investigated and analyzed. Each of the organizations is offering several kinds of E&T courses based on their own specific functions. These organizations have administrative facilities equipped with the latest technology for E&T in radiation protection. The E&T courses mainly cover the training courses for radiation workers, radiological emergency staff, license applicants, license holders, and regulatory staff. In 2010, a total of 58 E&T courses were carried out across six organizations. The conclusions make a number of observations highlighting challenges such as: establishing a formal feedback mechanism, introducing more practical training sessions, developing training courses tailored to the job categories and target audiences, and designing education and training courses in radiation protection that comply with current obligations as well as future requirements.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.267-268
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• 2002

Microbeam is a new avenue of radiation research especially in radiation biology and radiation protection. Selective irradiation of an ionizing particle to a targeted cell organelle may disclose such mechanisms as signal transaction among cell organelles and cell-to-cell communication in the processes toward an endpoint observed. Bystander effect, existence of which is clearly evidenced by application of the particle microbeam to biological experiments, suggests potential underestimation in the conventional risk estimation at low particle fluence rates, such as environment of space radiations in ISS (International Space Station). To promote these studies we started the construction of our microbeam facility (named as SPICE) to our HVEE Tandem accelerator (3.4 MeV proton and 5.1 MeV $^4$He$\^$2+/). For our primary goal, "irradiation of single particle to cell organelle within a position resolution of 2 micrometer in a reasonable irradiation time", special features are considered. Usage of a triplet Q magnet for focussing the beam to submicron of size is an outstanding feature compared to facilities of other institutes. Followings are other features: precise position control of cell dish holder, design of the cell dish, data acquisition of microscopic image of a cell organelle (cell nucleus) and data processing, a reliable particle detection, soft and hard wares to integrate all these related data, to control and irradiate exactly determined number of particles to a targeted spot.

• Environmental Analysis Health and Toxicology
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• 제24권3호
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• pp.203-211
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• 2009

A lesser degree of research is available with respect to indoor radon characteristics associated with occupants' exposure. The present study evaluated the radon levels in several public-access buildings or underground facilities, and their temporal variation in underground facilities. Radon measurements were conducted in 2005 and 2006, utilizing a continuous radon detector. A solid alpha detector (RAD7) was utilized to measure indoor radon levels. The mean radon concentrations obtained from the building or facilities were in a descending order: platforms of Daegu subway line 2, 2005 (32 $Bq/m^3$), hot-air bathroom (14 $Bq/m^3$), basement of office building (14 $Bq/m^3$), underground parking garage (14 $Bq/m^3$), underground shop (12 $Bq/m^3$), nursery (10 $Bq/m^3$), platforms of Daegu subway line 2, 2006 (9.0 $Bq/m^3$), platforms of Daegu subway line 1, 2006 (8.9 $Bq/m^3$), supermarket (7.9 $Bq/m^3$), hospital (7.3 $Bq/m^3$), and second-floor of office building (5.7 $Bq/m^3$). In general, underground-level facilities exhibited higher radon levels as compared with ground-level facilities. It was suggested that ventilation is an important parameter regarding the indoor levels of a subway. There was a decreasing or increasing trend in hourly-radon levels in a subway, whereas no trend were observed in a basement of office building. In addition, the radon levels in the subway lines 1 and 2 varied according to the platforms. The radon levels in the present study were much lower than those of previous studies. The average annual effective dose (AED) of radiation from indoor radon exposure was estimated to be between 0.043 and 0.242 mSv/yr, depending on facility types. These AEDs were substantially lower than the worldwide average AED (2.4 mSv/yr).

• Journal of Radiation Protection and Research
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• 제48권1호
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• pp.20-27
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• 2023

Background: As the number of nuclear facilities nearing their pre-determined design life increases, demand is increasing for technology and infrastructure related to the decommissioning and decontamination (D&D) process. It is necessary to consider the nature of the dismantling environment constantly changing and the worker doing new tasks. A method was studied that can calculate the effect of learning and the change in work time on the work process, according to the learning-forgetting curve model (LFCM). Materials and Methods: The LFCM was analyzed, and input values and scenarios were analyzed for substitution into the D&D process of a nuclear facility. Results and Discussion: The effectiveness and efficiency of the training were analyzed. It was calculated that skilled workers can receive a 16.9% less collective radiation dose than workers with only basic training. Conclusion: Using these research methods and models, it was possible to calculate the change in the efficiency of workers performing new tasks in the D&D process and the corresponding reduction in the work time and collective dose.

• Journal of Radiation Protection and Research
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• 제45권2호
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• pp.88-94
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• 2020

Background: The International Commission on Radiological Protection (ICRP) has recently published report series on the occupational intakes of radionuclides (OIR) for internal dosimetry of radiation workers. In this study, the optimized monitoring program including the monitoring interval and the minimum detectable activity (MDA) of major radionuclides was suggested to perform the routine individual monitoring of internal exposure based on the ICRP OIR. Materials and Methods: The derived recording levels and the critical monitoring quantities were reviewed from international standards or guidelines by the International Atomic Energy Agency (IAEA), the International Organization for Standardization (ISO), and the European Radiation Dosimetry Group (EURADOS). The OIR data viewer provided by ICRP was used to evaluate the monitoring intervals and the MDA, which are derived from the reference bioassay functions and the dose coefficients. Results and Discussion: The optimal monitoring intervals were determined taking account of two requirement conditions on the potential intake underestimation and the MDA values. The MDA requirement values of the selected radionuclides were calculated based on the committed effective dose from 0.1 mSv to 5 mSv. The optimized routine individual monitoring program was suggested including the optimal monitoring intervals and the MDA requirements. The optimal MDA values were evaluated based on the committed effective dose of 0.1 mSv. However, the MDA can be adjusted considering the practical operation of the routine individual monitoring program in the nuclear facilities. Conclusion: The monitoring intervals and the MDA as crucial factors for the routine monitoring were described to suggest the optimized routine individual monitoring program of the occupational intakes. Further study on the alpha/beta-emitting radionuclides as well as short lived gamma-emitting nuclides will be necessary in the future.

• 한국방사선학회논문지
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• 제12권3호
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• pp.305-312
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• 2018

유리 표면에 방사성동위원소 $^{14}C$를 고착시키고 문지름 시험을 통해 시험용지별 전이 인자와 표면 형상을 관찰하여 방사성동위원소 누설 점검을 위한 건식 및 습식 문지름 시험법을 연구하였다. 건식 문지름 시험법은 티슈 용지가 종이 필터를 대체 가능할 정도로 2배 높은 전이 인자를 보였고, 습식 문지름 시험법은 종이 필터 용지가 티슈 용지에 비하여 3배 높은 전이 인자를 보였다. 일반적으로 누설 점검을 위해 종이 필터를 사용하고 있지만 건식 문지름 시험법에서 티슈 용지가 대안이 될 수 있음을 보였다.

• 한국식품영양과학회지
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• 제35권3호
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• pp.383-387
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• 2006

호남지역 병원 6곳의 급식시설 및 부식류 등에 대한 미생물학적 안정성이 평가되어졌다. 조사된 병원급식시설의 공중낙하균 평가에서는 식탁, 조리장 및 냉동고에서 미생물균수가 비교적 높게 측정되어 이러한 시설에 대한 미생물학적 오염에 대한 철저한 관리가 요구됨을 보여 주었다. 또한 조리기구 및 용기 표면의 미생물학적 안정성 측정에서는 도마, 칼, 식판 등의 일반세균수는 비교적 높았으나 유의적인 수준은 아니었으며 대장균군, 황색포도상구균, 대장균 등의 수준도 일반적인 미생물 오염기준 미만으로 나타나 미생물학적 안정성은 양호하였다. 하지만 이들 급식시설에서 제공되는 부식류에 대한 미생물학적 안정성 평가에서는 대체적으로 가열조리식품의 미생물학적 오염은 기준 미만으로 나타났으나 기준을 초과한 부식에 대해서는 철저한 미생물학적 안전 관리가 이루어져야 할 것으로 판단되었다.

• 한국방사선학회논문지
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• 제17권4호
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• pp.489-495
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• 2023

방사선 방어시설은 진단용 방사선 발생장치가 설치되어 있는 장소에 구축되어 환자, 방사선 작업 종사자 등의 피폭을 방지한다. 본 연구에서는 이러한 방사선 방어시설의 주 재료인 납에 대해 최대관전압별 차폐 두께의 경향성을 몬테칼로 시뮬레이션과 실측을 통해 비교 검증하고자 한다. 몬테칼로 시뮬레이션 코드 중 Monte Carlo N-Particle 6를 활용하였으며 해당 시뮬레이션 상에 모사한 납 차폐 구조도는 선원과 납 시트 사이의 거리는 100 cm, 조사야 크기는 10 × 10 cm²이며 관전압은 80, 100, 120, 140 kVp로 설정하였다. 각 관전압별 에너지 스펙트럼을 산출하여 시뮬레이션에 적용하였다. 80, 100, 120, 140 kVp별 각각 50, 70, 90, 95% 차폐율을 보이는 납 두께를 산출하였다. 80 kVp에서 각 차폐율에 해당하는 두께는 각각 0.03, 0.08, 0.2 1, 0.33 mm이며, 100 kVp에서는 0.05, 0.12, 0.30, 0.50 mm, 120 kVp에서는 0.06, 0.14, 0.38, 0.56 mm, 140 kV p에서는 0.08, 0.16, 0.42, 0.61 mm로 나타났다. 산출된 납 두께에 대해 실측을 진행하였으며 사용된 방사선 발생장치는 GE Healthcare 사의 Discovery XR 656이며 선량계측기의 경우 IBA 사의 MagicMax이다. 실측결과 80 kVp에서 각 두께별 차폐율은 43.56, 70.33, 89.85, 93.05%였으며 100 kVp에서는 52.49, 72.26, 86.31, 92.17%, 120 kVp에서는 48.26, 71.18, 87.30, 91.56%, 140 kVp에서는 50.45, 68.75, 89.95, 91.65%.로 나타났다. 시뮬레이션과 실측을 비교한 결과 두 값의 차이가 평균 약 3% 이내로 작은 것으로 확인되었다. 본 연구의 결과는 몬테칼로 시뮬레이션의 신뢰성을 검증함과 동시에 향후 방사선 방어시설의 구축에 있어 기초 데이터로 활용될 수 있을 것으로 사료된다.

• Nuclear Medicine and Molecular Imaging
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• 제41권4호
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• pp.309-316
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• 2007

감시 림프절 생검은 유방암 수술에서 림프절 전이 상태를 알기 위한 표준 시술이다. 환자는 방사성 콜로이드를 주사 받은 후 수술을 받게 된다. 이 과정에서 검사를 하는 핵의학과, 수술장, 유방암 검체를 다루는 병리과의 관계자는 미량이나마 환자와 검체에 의해서 방사선 피폭을 받을 수 있다. 이 연구의 목적은 감시 림프절 생검 과정, 특히 병리처리 과정에서 받는 방사선피폭을 정량하여 그 안전성을 확인하고 병리 시설과 폐기물에 대해서도 방사선 관련 안전성을 확인하는 것이다. 대상 및 방법 : 감시림프절 생검은 방사성 콜로이드를 이용하여 일반적인 임상적 방법으로 시행되었다. 병리기사, 핵의학 기사 및 핵의학 의사의 피폭량을 열형광선량계를 이용하여 1달간 측정하였다. 또한 작업과정중의 잔존 방사능량, 흡수선량, 작업시간, 작업거리, 조직폐기물 및 병리검사실의 공간선량을 측정하였다. 결과 전신 및 손의 피폭량은 병리기사에서 각각 0.21 및 0.85 uSv/study이었고 핵의학과 의사 및 핵의학과 기사의 전신피폭량은 각각 0.2 및 2.3 uSv/study 이었다. 일반인 기준(1000 uSv/year)으로 병리기사는 년간 약 1100건 감시림프절 관련 검체 처리를 할 수 있었다. 각 과정의 잔존방사성 및 피폭거리, 시간으로 측정한 피폭량은 수술의사는 전신/손의 피폭량이 건당 2.47/22.4 uSv 이었고 수술장간호사는 건당 0.22/0 uSv 이었다. 병리실의 공간선량률은 0.02-0.03 mR/hr로 방사성 관리구역의 설정 기준에 도달하지 않았다. 폐기되는 검체 조직의 방사능은 거의 측정되지 않아 100 Bq/g에 훨씬 미치지 않았다. 결론: 방사성동위원소를 이용한 감시림프절 검사에 관계된 병리처리과정은 방사선안전측면에서 일반적으로 안전하며 별도의 안전관리나 시설 없이 이루어 질 수 있다.