Earticle

원료물질 또는 공정부산물을 가공하거나 이를 원료로 하여 제조된 제품인 가공제품은 함유된 천연방사성핵종(우라 늄, 토륨, 포타슘 등)으로부터 감마선 방출로 외부피폭을 유발할 수 있다. 따라서 본 연구에서는 방사성핵종 농도 우라늄·토륨 1 Bq·g-1, 포타슘 10 Bq·g-1을 가정하고 평형상태의 감마선방출을 가정하여 최종사용자의 사용환경을 반영하여 몬테칼로 전산모사로 복셀팬텀인 ICRP 기준팬텀과 ICRP 권고 103을 적용하여 가공제품의 연간피폭선량을 계산하고 체계를 개발하였다. 가공제품은 사용환경에 따라 피부비밀착형(석고보드, 음이온 벽지, 음이온 페인트)과 피부밀착형(팔찌, 목걸이, 벨트, 뜸질기)으로 구분하였고 기하학적 모델링은 일반가구가 거주하는 주택의 유형 분포 추이와 설계지침을 반영하여 룸모델링(3 m×4 m×2.8 m 보수적으로 밀폐된 방)과 복셀팬텀 분할면에 직접 가공제품을 모사하였다. 사용시간은 한국형 노출지수 개발 및 운영체계 구축 보고서를 참고하였으며 알 수 없는 제품은 보수적 으로 24시간을 가정하였다. 본 연구에서 가공제품의 연간 유효선량은 0.00003 ∼ 0.47636 mSv로 평가되었으며 벨트 류 장기등가선량률을 확인하여 복셀팬텀에 가공제품을 직접 모사하는 것의 의미를 확인하였다.

Radiation exposure to humans can be caused by the gamma rays emitted from natural radioactive elements(such as uranium, thorium and potassium and any of their decay products) of Naturally Occurring Radioactive Materials(NORM) or Technologically Enhanced Naturally Occurring Radioactive Materials(TENORM) added consumer products. In this study, assume that activity of radioactive elements is 238U, 235U, 232Th 1 Bq·g-1, 40K 10 Bq·g-1 and the gamma rays emitted from these natural radioactive elements radioactive equilibrium state. In this study, reflected End-User circumstances and evaluated annual exposure dose for products based on ICRP reference voxel phantoms and ICRP Recommendation 103 using the Monte Carlo Method. The consumer products classified according to the adhere to the skin(bracelet, necklace, belt-wrist, belt-ankle, belt-knee, moxa stone) or not(gypsum board, anion wallpaper, anion paint), and Geometric Modeling was reflected in Republic of Korea “Residential Living Trend-distributions and Design Guidelines For Common Types of Household.”, was designed the Room model(3 m×4 m×2.8 m, a closed room, conservatively) and the ICRP reference phantom`s 3D segmentation and modeling. The end-user`s usage time assume that “Development and Application of Korean Exposure Factors.” or conservatively 24 hours; in case of unknown. In this study, the results of the effective dose were 0.00003 ∼ 0.47636 mSv per year and were confirmed the meaning of necessary for geometric modeling to ICRP reference phantoms through the equivalent dose rate of belt products.

To develop tailored elementary, middle, and high school textbooks suitable for understanding the nuclear energy and radiation, quantitative and qualitative research was carried out in parallel, which included nine steps to ensure the validity of content and structure. The elementary, middle, and high school students wanted to acquire information used in their daily lives, including the definition of nuclear energy and radiation, principles and status of nuclear power generation, and information about irradiated food, medical radiation, and radiation in life. In the evaluation of the effects of textbook contents according to the educational requirements of each school level, high suitability frequencies (>80%) were shown for the human character, education goals, curriculum goals, evaluation method, and education time. At some levels, the high suitability frequencies (>70%) were shown for the education grade, education type, and textbook type.

The scatter photons and photoneutrons from high energy photon beams (more than 10 MV) will increase the undesired dose to the patient and the staff working in linear accelerator room. This undesired dose which is found at out-of-field area can increase the probability of secondary malignancy. The purpose of this study is to determine the equivalent dose of scatter photons and neutrons generated by 3 different treatment techniques: 3D-conformal, intensity modulated radiation therapy (IMRT) and volumetric modulated arc therapy (VMAT). The measurement was performed using two types of the optically stimulation luminescence detectors (OSL and OSLN) in the Alderson Rando phantom that was irradiated by 3 different treatment techniques following the actual prostate cancer treatment plans. The scatter photon and neutron equivalent dose were compared among the 3 treatments techniques at the surface in the out-of-field area and the critical organs. Maximum equivalent dose of scatter photons and neutrons was found when using the IMRT technique. The scatter neutrons showed average equivalent doses of 0.26, 0.63 and 0.31 mSv․Gy-1 at abdominal surface region which was 20 cm from isocenter for 3D, IMRT and VMAT, respectively. The scattered photons equivalent doses were 6.94, 10.17 and 6.56 mSv․Gy-1 for 3D, IMRT and VMAT, respectively. For the 5 organ dose measurements, the scattered neutron and photon equivalent doses in out of field from the IMRT plan were highest. The result revealed that the scatter equivalent doses for neutron and photon were higher for IMRT. So the suitable treatment techniques should be selected to benefit the patient and the treatment room staff.

Radon is a naturally occurring radioactive gas and a major indoor contribution of exposure to ionizing radiation in dwellings. 222Rn is a health hazard gas what is responsible for thousand lung cancer deaths every year. In this study, indoor radon concentrations present in thirty representative houses in Mahallat city, Iran, were determined in order to estimate lung cancer risk associated with residential radon exposure. Long-term passive method, using CR-39, was used to measure the radon concentration. The results showed an association between the age of the dwellings and the indoor radon concentration that was found, in that the concentration of radon tended to increase as the age of the dwelling also increased. The indoor radon concentrations were calculated to be within the range of 23±2 to 350±26 Bq․m-3, with an average of 158 Bq․m-3. The annual effective dose from inhaled radon and its decay products was calculated between 0.8±0.1 and 12.3±0.9 mSv․y-1, with an average of 5.5 mSv․y-1. By taking into consideration the EPA recommendation and ICRP statement, the average annual risk of lung cancer from inhaled radon was calculated as 0.09%, 0.06%, 0.01%, and 0.03% for current smokers (CS), those who had ever smoked (ES), never smokers (NS) and the general population, respectively.

후쿠시마 원전 사고로 인한 우리나라 장기 전력수급정책에 대한 대중의 저항 및 불안감이 존재하고 있다. 고리 원전 1호기에 대한 정부의 영구정지 결정과 설계수명이 끝난 월성 원전 1호기의 계속운전 시행 반대, 고리 원전 인근 주민 의 갑상선암 논란 등 원전 운영으로 인한 국내외 여건이 위기를 맞이하고 있다. 이러한 상황에서 원전운영능력과 안 전은 여러 가지 지표들이 있지만, 원전의 방사선안전관리 능력, 특히 방사선피폭량을 중심으로 상세 분석과 논의가 필요하다. 분석대상과 방법으로는 최근 5년간 원전의 피폭 방사선량을 분석하고, 유관한 방사선 작업종사자군과 방 사선 피폭량 추이를 비교 평가하였고, 세계 주요 원전 국의 개인당 연간 평균방사선량도 비교 분석하였다. 분석결과 방사선차폐와 방호조치등 총체적인 방사선량 저감화 계획과 연구를 통해 방사선피폭량을 저감하고 있음을 확인하였 다. 연간선량한도한도인 50 mSv, 5년간 100 mSv를 초과한 방사선작업 종사자는 없었으며, 이는 방사선구역 출입시 자동화에 따른 출입제한과 관리선량 제한치를 연간선량한도의 60%미만으로 설정하는 등 다양한 방사선안전관리 체 계를 확보하고 있음이 확인되었다. 원자로형별 운영형태에 따른 방사선피폭 유형은, 중수로 원전의 총 피폭대비 정상 운전시 방사선피폭비율이 경수로 원전보다 6.2 % 높게 나타났다. 이는 중수로 원전이 정상운전시 방사선피폭 작업이 많음을 확인하였다. 또한 세계원자력발전사업자협의회 성능평가지표(World Association of Nuclear Operators performance indicators, WANO PI)에 의하면, 2013년도 주요 원전보유국의 연간 호기당 집단선량은 우리나라가 527 man-mSv로 가장 우수한 실적을 보였으며, 세계평균치인 725 man-mSv의 73% 수준을 보이는 것으로 나타났다. 개인 당 연간 방사선피폭량은 종사자의 약 80%가 일반인의 선량한도인 1 mSv 미만이며, 개인당 평균선량 역시 0.82 mSv 로 매우 낮은 수준을 보였다. 유관 기관의 방사선작업 종사자와 비교해보면, 2013년 기준으로 방사선안전재단에 등 록된 관련 업종 방사선작업 종사자의 개인당 평균선량은 1.07 mSv에 비해 77% 수준이며, 비파괴 검사기관 종사자의 개인 평균선량 3.87 mSv의 21% 수준을 보였다. 결론적으로 원전의 피폭 방사선량은 이상적으로 저감하는 추이를 보 이고 있으나, 더 이상 낮추는 것은 한계가 있을 것으로 판단된다. 그러나 원전 주변 주민이 심리적인 불안감, 전원 개발계획에서 원전의 비중을 감안할 때, 최적의 원전 상황을 평가하는 지표인 방사선안전관리 능력은 각종 통계를 기반으로 하는 정보 제시 및 총체적인 방사선량 저감화 추진이 필요할 것으로 판단된다.

Although the perfomance indicators of the nuclear power plants in Korea show optimal, it requires detailed analysis and discussion centered on the radiation dose. As analysis methods, analysis on the radiation dose of nuclear power plants over the past five years was assessed by comparing the relevant radiation dose of radiation workers and per capita average annual radiation dose of the world's major nuclear power stations was also analyzed. The radiation workers over the annual radiation dose limit of 50 mSv were not. The contrast ratio of the radiation exposure according to the reactor type was the normal operation of PHWR was 6.2% higher than those of the PWR. This shows the radiation work of PHWR during normal driving operation is much more than those of PWR. According to the Performance Indicators of the World Association of Nuclear Operator, the annual radiation dose per unit in 2013 showed 527 man-mSv of Korea is the best country among the major nuclear power generating states, the world average was 725 man-mSv. The annual per capita radiation dose is about 80% less than 1 mSv of the public dose limit and also the average per capita dose showed a very low level as 0.82 mSv. Workers in related organizations showed 1.07 mSv, the non-destructive inspection agency workers showed 3.87 mSv. The remarkable results were due to radiation reduced program such as development of radiation shielding and radiation protection. In conclusion, the radiation exposured dose of nuclear power plants workers in Korea showed a trend which is ideally reduced. But more are expected to be difficul and the psychological insecurity against the operation of the nuclear power plants is existed to the residents near the nuclear power plants. So the radiation dose reduction policy and radiation dose follow up study of nuclear power plants will be continously excuted.

이 연구에서 후쿠시마 원전 폭발과 같은 사고 발생 시 방사선이나 방사성 핵종에 의한 생물학적 영향을 평가할 수 있는 야생 동물지표로서 성축 등줄쥐(A. a. coreae) 활용 가능성을 평가하였다. 이 연구를 위하여 야외 채집한 등줄 쥐를 실험실에서 교배하고 생산된 새끼가 약 40주령이 되었을 때 털 색깔, 외부형태, 두개골, 치아 특성을 관찰하고 분류학적 특성을 정리하였다. 방사선에 대한 신체 반응도를 평가하기 위하여 방사선 조사(0, 0.5, 1, 2 Gy) 24시간 후에 장기무게를 관찰한 결과 흉선만이 감소하였다. 방사선에 민감한 장기 가운데 하나인 비장 세포고사는 선량에 비례하여 증가하였지만, 0.5 Gy 조사된 개체에서는 감소하였다. 앞으로 야생 등줄쥐 신체 장기별 방사선 민감도 차 이를 세포 및 분자생물학적 수준에서 해석함으로써 방사선 피폭 사고시 신체영향을 평가할 수 있는 방법론 도출이 가능할 것이라 생각된다.

The present investigation was planned to estimate potential possibility of striped field mice, Apodemus agrarius coreae (A. a. coreae), as a biological dosimeter in radio-environmental ecology. We bred captured wild A. a. coreae at laboratory and classified taxonomically based on external, cranial and tooth characters. Organ weights and splenocytic apoptosis were observed in order to establish a basic data on radiation biology of A. a. coreae (male, 40 weeks old). The biological effects was observed at 24hrs following irradiation (doses : 0, 0.5, 1, 2 Gy, dose rate : 0.8 Gymin-1, 137Cs). Only thymus weights was significantly decreased. Splenocytic apoptosis was increased after irradiation. But splenocytic apoptosis was decreased in 0.5 Gy γ-irradiated mice compared to those of 0, 1, 2 Gy (P 〈 0.05). These data suggested that events in thymus and spleen of Korean dark-striped field mice, A. a. coreae THOMAS, could be a potential radio-biological indicator in human environments.

예비 방사선 작업 종사자인 방사선학과 대학생을 대상으로 방사선 기초 개념과 공간선량 인식, 방사선 안전 인식에 대해 알아보고자 하였다. X선 촬영 실습실에서 X선 조사 시 발생하는 공간선량을 학생들이 직접 측정함으로써 방사 선 기초 개념과 공간선량 인식에 따른 실험 전·후의 방사선 안전 인식 변화를 파악하고자 하였다. 그 결과 실험 후 에 학생들의 방사선 안전 인식이 보수적이고 엄격하게 변화하는 것을 알 수 있었다. 그럼에도 불구하고 방사선학과 대학생들의 경우 방사선 안전 인식 보다 직업의식이 앞서는 형태를 볼 수 있었는데 이는 의료적 이용에 따른 이득을 우선적으로 고려한 결과로 생각된다. 이에 따라 의료적 이익의 범위 내에서 방사선 이용에 따른 세분화된 안전교육 프로그램이 필요성이 요구된다. 따라서 시청각 자료를 이용한 단순한 강의 중심의 안전 교육이 아닌, 직접 공간선량 측정 실험과 같은 체험적 안전 교육 프로그램을 제안하는 바이며 방사선 안전 인식의 보수적인 관점과 엄격한 태도 를 지향하는 직업의식 교육이 필요한 것으로 파악되었다.

There are currently many research papers on the knowledge, perceptions and actions of radiation-related staff, but hardly any papers on radiation major students in college who are to be staff members of radiation related jobs in the future. It is of course important to understand the perceptions of staff working on the lines and change their knowledge and perceptions, but in the long term it seems more efficient to understand those who are in the stage of being educated to be staff members—their knowledge and perception of radiation so that ultimately they can attain the right kind of understanding. Therefore the aim of this study is to grasp the pre-radiation staff’s basic concept of radiation and space dose, their understanding of radiation safety based on this, and whether there is a change in their perception before and after the space dose measurement experiment; in the end this is to see if the space dose measurement experiment is effective in changing perception on radiation safety. This study took as its subject 64 students majoring radiation in college, I.e. pre-radiation staff members, and gauged their basic conceptualization of radiation, understanding of space dose, and understanding of radiation safety; in the X-ray room within the department the students were asked to measure space dose for themselves, so as to see whether there was a change in their understanding of radiation safety before and after the experiment, according to their understanding of the basic concept of radiation and of space dose. As a result of the space dose measurement experiment, students’ increased basic knowledge of concept of radiation and understanding of the dangers of space dose were noteworthy, and accordingly their understanding of radiation safety became stricter and more conservative. In spite of this, their work ethic stayed in the lead of their understanding of radiation safety; this implies the need of a more departmentalized safety education program. Therefore instead of safety education that simply uses visual- audial material in a kind of lecture, I suggest here that there be a more experiential safety education program that enables learners to try out space dose measurement experiments for themselves, a work ethic education that aims for a conventional point of view towards radiation safety as well as a stern attitude.

방사성 제논 탐지는 공기 중 131mXe, 133Xe, 133mXe 및 135Xe를 저준위 백그라운드 계측 시스템으로 검출하여 지하 핵실험 여부를 규명하는 핵심기술 중 하나이다. 방사성 제논 감시는 공기 포집, 제논 추출, 측정 및 분석을 통해 수행 되며, 135Xe의 최소검출가능농도는 비교적 짧은 반감기로 인해 포집, 추출 및 측정시간에 따라 큰 차이를 보이게 된 다. 본 연구에서는 방사성 제논 계측 시스템의 정해진 시료 포집 및 전처리 조건에서 최적의 방사성 제논 측정시간을 도출하기 위해 이론적 접근 및 SAUNA 시스템을 이용한 실험을 통해 최소의 MDC를 보이는 측정시간을 결정하고 이 론적 계산과 실험결과에 대하여 비교·평가하였다.

Measurement of xenon radioisotopes from nuclear fission is a key element for monitoring underground nuclear weapon tests. 131mXe, 133Xe, 133mXe and 135Xe in the air can be detected via low background systems such as a beta-gamma coincidence counting system. Radioxenon monitoring is performed through air sampling, xenon extraction, measurement and spectrum analysis. The minimum detectable concentration of 135Xe can be significantly variable depending on the sampling time, extraction time and data acquisition time due to its short half-life. In order to optimize the acquisition time with respect to certain experimental parameters such as sampling and xenon extraction, theoretical approach and experiment using SAUNA system were performed to determine the time to minimize the minimum detectable concentration, which the results were discussed.

Deleterious effects of high dose radiation exposure with high-dose-rate are unarguable, but they are still controversial in low-dose-rate. The regulator of G-protein signaling (RGS) is a negative regulator of G proteincoupled receptor (GPCR) signaling. In addition, it is reported that irradiation stress led to GPCR-mediated mitogen-activated protein kinase (MAPK) and phosphotidylinositol 3-kinase (PI3-k) signaling. The RGS mRNA expression profiles by whole body radiation with low-dose-rate has not yet been explored. In the present study, we, therefore, examined which RGS was modulated by the whole body radiation with low-dose-rate (3.49 mGy·h-1). Among 16 RGS expression tested, RGS6, RGS13 and RGS16 mRNA were down-regulated by low-dose-rate irradiation. This is the first report that whole body radiation with low-dose-rate can modulate the different RGS expression levels. These results are expected to reveal the potential target and/or the biomarker proteins associated with male testis toxicity induced by low-dose-rate irradiation, which might contribute to understanding the mechanism beyond the testis toxicity.