In Korea, Kori Unit 1, a commercial pressurized water reactor (PWR), was permanently shut down in June 2017, and an immediate decommissioning strategy is underway. Therefore, it is essential to understand the characteristics of radioactive waste during the decommissioning process of nuclear power plants (NPP). Because radioactive waste must be handled with care, radioactive waste is treated in a hot cell facility. Hot cell facility handles radioactive waste, and worker safety is essential. In this study, it was dealt with whether or not the radiation safety regulations were satisfied when processing the core beltline metal of the dismantling waste treated at the post irradiation examination facility (PIEF) of the hot cell facility. Core beltline metal used for the pressure vessel in the reactor is carbon steel, and it is continuously irradiated by neutrons during the operation of the NPP. A radiological safety estimation of the behavior of radioactive aerosols during the cutting process within the PIEF was carried out to ensure the safety of the environment and workers. When processing the core beltline metal in PIEF, dominant six nuclides (60Co, 63Ni, 55Fe, 3H, 59Ni, 14C) of aerosol are generated. Accordingly each cutting device, amount of aerosol and value of dose is different. Using a 99.97% efficiency HEPA filter, the emission concentration of the dominant nuclides (60Co, 63Ni, 55Fe, 3H, 59Ni, 14C) in the air source term was satisfied with the emission control standard of Nuclear Safety Commission No. 2016-16. It was confirmed that the radioactivity concentration in the airborne source term inside the PIEF is in equilibrium state, when ventilation is considered. Also, the mass of aerosol and the concentration of airborne source term differed according to the thickness of the saw blade of the cutting tool, and the exposure dose of the worker was different through Monte Carlo N-Particle (MCNP). At that time, 60Co accounted for 95.4% of the exposure dose, showing that 60Co had the highest impact on workers, followed by 55Fe with 2.7%. The worker’s dose limit is satisfied in accordance with Article 2 of the Nuclear Safety Act and the dose limit of radiation-controlled area is found to be satisfied in accordance with Article 3 of the rules on technical standards for radiation safety management at this time.

It is essential to provide a safe working environment for radiation workers. At a research reactor decommissioning site in Seoul (KRR1 & KRR2), radioactive waste drum disposal work is in progress. Before performing radiation work, it is necessary to determine the radioactivity of the waste drum to ensure safety. In this reason, we conducted a study to determine the detection efficiency of waste drums using the EXVol code. Determination of the full energy absorption peak efficiency (detection efficiency) is one of the important processes of the gamma-ray activation analysis. For the large voluminous gamma-ray sources like waste drum, the geometrical and attenuation effect should be considered. EXVol (Efficiency calculator for eXtended Voluminous source) code is a detection efficiency calculation code using the effective solid angle method. EXVol can calculate both coaxial and asymmetric structure. In addition, the introduction of a collimator made it possible to reduce the radiation intensity of a high radiation source. And it is possible to determine the precise detection efficiency according to the energy of a gamma ray at a specific position of the volume source. To verify the performance of the EXVol, a high resolution gamma spectroscopy system was constructed and measurement and analysis were performed. Measurements were performed on coaxial, asymmetric and collimated structures with standard point source, standard 1 L liquid volume source and HPGe detector. The measured results were compared with the calculation results of EXVol. The relative deviation of the measurement and calculation in the coaxial and asymmetric structures was 10%, and that of the collimation structure was 20%. Results can be available in analysis of waste drums’ radioactivity determination at a specific position.

To investigate the perceptions and attitudes of dental hygienists toward radiation safety management in Korea. A total of 800 dental hygienists were randomly selected for an anonymous survey, and 203 of them participated. The questionnaire items included the following: sex, career period, type of installed radiographic equipment, recognition of the diagnostic reference level (DRL), participation in radiation safety education, and attitudes toward radiation protection for both patients and dental hygienists. The participants were divided into two groups according to their years of experience (< 10 years versus ≥ 10 years). The difference between the groups was investigated according to frequency distribution. Fisher’s exact test or Pearson’s chi-square (χ2) test was used as appropriate. A regression analysis was performed to investigate the impact of wearing a thyroid collar for personnel protection during patient radiation exposure. The types of installed radiographic equipment included panoramic radiography (96.1%), cephalometric radiography (76.9%), intraoral radiography (72.9%), and cone-beam computed tomography (69.5%). Significant differences were observed in the learning pathway for the DRL (Fisher’s exact test, p < 0.05), satisfaction with radiation safety education (Pearson’s χ2 test = 5.3975, Pr = 0.02), and use of personnel radiation monitoring systems (Pearson’s χ2 test = 18.1233, Pr = 0.000) between the groups. Significant differences were also observed in personnel protection using a thyroid collar and patient protection during panoramic radiography (odds ratio = 14.2). Dental hygienists with more than 10 years of experience were more satisfied with radiation safety education and more interested in radiation monitoring. Considering career experience, customized, continuous, and effective radiation safety management education should be provided.

본 연구에서는 최근 개발중인 360 다발 장전용량의 중수로 사용후핵연료 운반용기에 대한 설계기준연료의 방사선원항 평가와 용기외부에서의 방사선량률 계산을 수행하였다. 그리고 국·내외 방사선적 안전성평가와 관련한 기술기준 부합여부를 판단하고 결과의 적합성을 제시하였다. 방사선원항으로 작용하는 설계기준연료 선정을 위해 월성원전에서 운영중인 운반 용기 및 두 가지 방식의 건식저장시설에 적용된 설계기준연료의 사양 및 특성을 조사하였다. 각 운반·저장 시스템 별 설계 기준연료의 연소도, 최소 냉각기간 및 중간저장시설로의 운반시점 등을 바탕으로 연소도 7,800 MWD/MTU와 최소 냉각기 간 6년을 설계기준연료로 설정하였다. 설계기준연료의 방사선원항은 SCALE 전산코드의 ORIGEN-ARP모듈을 이용하여 평가하였다. 운반용기의 방사선차폐평가는 MCNP6 전산코드를 이용하였으며, 기술기준에서 요구하는 운반용기 외부에서의 방사선량률 평가를 정상 및 사고조건으로 구분하여 수행하였다. 방사선량률 평가결과, 정상운반조건의 운반용기 표면 및 운반용기 표면 2 m 이격지점에서 계산된 최대 방사선량률은 각각 0.330 mSv·h-1와 0.065 mSv·h-1로 도출되어 선량률 제한치인 2.0 mSv^hr-1와 0.1 mSv^hr-1를 모두 만족하는 결과를 도출하였다. 또한 운반사고조건하 운반용기 표면 1 m 지점에서의 최대 방사선량률은 0.321 mSv·h-1로서 기술기준인 10.0 mSv·h-1 미만으로 평가되어, 대용량 중수로 사용후핵연료 운반용기는 방사선적 안전성을 확보하는 것으로 나타났다.

This study implemented the survey and analysis of the exposure to radiation by using the questionnaire targeting H Health College, located in Daejeon from September 1st, 2014 to October 15th. A total of 400 copies of the questionnaire was distributed and among them, 385 copies, excluding 15 omitted ones (total collection ratio: 96.3%), were used for the analysis. The analysis results are as follows. For the harmfulness of radiation for diagnosis, the average of the health-related was 3.15 and the average of the health-unrelated was 2.82, which the health-related students recognized the harmfulness of radiation for diagnosis higher (p<.001). The necessity of radiation for diagnosis was appeared higher from the health-related students as the average of the health-related was 3.07 and 2.52 for the average of the health-unrelated (p<.001). The recognition on the prevention of the exposure to radiation was higher from the health-related students as the average of the health-related was 3.13 and 1.84 for the average of the health-unrelated (p<.001). From this study, the necessity of using radiation from the medical field and the recognition on its harmfulness appeared to have a big difference between the health-related and health-unrelated. For such, the accurate understanding of the recognition on radiation and the education to improve recognition on radiation are considered to be required.

The purpose of this study was to investigate the actual conditions of radiation safety supervision in animal clinics using inspection standard of X-ray generator for diagnosis. The surveys for inspection standard system, equipment condition, and safety supervision were carried out in 18 animal clinics randomly. The inspection standard included reproducibility of dose exposure, kVp, mAs, collimator accuracy test, collimator luminance test, X-ray view box luminance test, grounding system equipment test and external leakage current test. The surveys of equipment condition and safety supervision used one-on-one interview with 5 points measurement. As a result, 44.44% of reproducibility of dose exposure was proper, 81.25% of kVp test was good, and 100% of mAs test was appropriate. Also, 66.66% of collimator accuracy test was proper, 61.11% of collimator luminance test was good, 53.13% of X-ray view box luminance test was suitable. In addition, only 5.55% of grounding system equipment and ground resistance was proper, 63.64% of external leakage current test was appropriate in grounding system equipment test. The 100mA electric capacity of X-ray generator for diagnosis was popular with 44.44%, and its 55.56% was purchased used equipment. Monthly average of less than 50 times (61.11%) was top frequency in use, and no animal clinic had a thermo-luminescence dosimeter(TLD). The 16 animal clinics with radiation safety zone and 2 without radiation safety zone were appeared.

1895년에 독일 뢴트겐에 의해 발견된 이후 X선은 1896년부터 의료목적으로 사용된 기록이 있으며, 한국에 도입되어 진단용X선발생장치로서 환자 진료에 사용하기 시작한 역사는 1911년경부터 조선총독부의원과 세브란스의원에 도입되어 사용하게 되었다. 최근 의학 및 의용공학의 발전으로 방사선을 이용한 진단 기술의 발전과 건강에 대한 국민의 의료욕구가 증가함에 따라 방사선을 이용한 질병의 진단과 치료 방법에서 새로운 기법이 개발되고 그 이용은 지속적으로 증가되고 있는 추세이다. 방사선의 이용은 진단 및 치료에 중대한 이득을 제공하고 있으나 그 이면에는 최적화 및 정당화 되지 않은 방사선의 피폭으로 장애 및 유해요인이 초래되는 것은 부인할 수 없다. 이와 관련하여 방사선을 이용하여 검사 및 치료를 시행함에 있어 피폭선량 최적화를 위한 기술적 노력은 방사선 관계자의 막중한 의무이다.

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.

본 연구의 목적은 교육용 치과 엑스선 발생장치를 설치 및 가동 중인 전국 치위생(학)과를 대상으로 방사선 작업종사자의 방사선 안전 관리 실태를 설문 조사하고 이를 체계적으로 추이 분석하여 교육용 치과 엑스선 발생장치의 안전한 이용 기반을 확립하기 위한 기초 자료로 제공하고자 하였다. 이를 위하여 교육용 치과 엑스선 발생장치의 방사선 안전 관리와 관계되는 원자력 관계 법령 및 국내 방사선 안전성 평가 및 규제 기술 개발 현황에 대한 용역 보고서를 참고하여 포괄적인 문헌 조사를 하였으며 이를 토대로 응답자의 일반적 특성, 방사선안전관리자의 위상, 방사선 안전관리 현황과 지식 및 의식 수준에 대한 설문지를 작성하였다. 본 연구는 국내 교육기관 내 방사선안전관리자와 교육용 치과 엑스선 발생장치를 운전 가능한 학사 및 실습 조교, 전임 교원 224명을 대상으로 설문 조사를 시행하여 설문 응답 누락 및 불충분한 응답을 제외한 95부를 회수하여 분석 자료로 이용하였다. 분석 방법은 일반적 특성 및 방사선안전관리자의 위상은 빈도와 백분율을 구하였으며 방사선 안전 관리 현황과 지식 및 의식 수준은 빈도 분석과 설문 문항별 연관성 분석을 위한 χ2 검정(chi-square test)과 수준간 연관성을 구하기 위한 피어슨 상관분석(Pearson correlation analysis)을 하였다. 결과적으로 교육용 치과 엑스선 발생장치의 운영은 대부분 대학 이상의 사회적 교육 수준이 높고 치위생학을 전공한 20대에서 40대의 여성이 담당하고 있었으며 남성과 비교하여 방사선 안전 관리에 대한 의식 수준이 높게 나타났으며 통계적으로 유의한 선형적 관계를 보였다(χ2 >5, 0.1<r<0.3, p<0.05). 또한 국가 기술 면허의 보유는 치과위생사가 55.4%로 가장 많았으나 방사성동위원소 취급자 일반 면허자(28.2%) 또는 방사선사 면허자(16.4%)와 비교하여 방사선 안전 관리에 대한 의식 및 지식 수준이 낮게 나타났으며 통계적으로 유의하게 뚜렷한 선형적 관계를 보였다(χ2 >5, 0.3<r<0.7, p<0.01). 특히 업무 경력이 증가할수록 방사선 안전 관리에 대한 지식은 높게 나타났으나 의식 수준은 감소하는 것으로 분석되었다(χ2 >5, 0.3<r<0.7, p<0.01). 따라서 방사선 안전 관리에 대한 전문적 지식 체계의 확립과 국내 외 방사선 안전 관리 체계를 포괄적으로 이해할 수 있는 제도화된 개선책 마련이 시급할 것으로 판단되었으며 교육용 치과 엑스선 발생장치의 사용에 따른 방사선작업종사자와 주변 일반인의 방사선 위해로부터 방어를 위한 체계적인 방사선 안전 관리 지침서의 개발이 필요하다고 판단되었다.

최근 시행된 생활주변방사선안전관리법에 제시된 항목들을 분석하고자 하였다. 실험 항목을 우주방사선, 지각방사선, 공정부산물 등으로 나누고, 그에 따른 측정 장소를 상공 8000m의 비행기, 해발 1000m의 산악지대, 지하 15m 건 물, 건설 현장, 해발 0m의 바닷가를 선정하였다. 실험결과 우주방사선을 기준으로 상공 8000m 비행기에서는 유효선량이 연간 2.45mSv로 측정되었다. 우주방사선 과 지각방사선의 측정 장소로 선정된 해발 1000m 산악지대는 기준점인 0m인 바닷가에 비해 0.17mSv 높게 측정되었 다. 공정부산물의 측정 장소로 선정된 건설 현장은 3.32mSv로 실험항목 중 가장 높은 수치를 나타내었다. 이는 완공 된 건물 보다 약 5배 정도 높은 선량이라는 것을 알 수 있었다. 해발 0m인 바닷가는 2.89mSv로 측정되었고, 지각 방 사선을 기준으로 설정된 지하 15m 건물에서는 2.36mSv로 가장 낮게 측정되었다. 이를 통해, 지하로 내려갈수록 지각 방사선을 많이 받을 것으로 예상되었으나 건물 안에서의 지각 방사선은 크게 영향을 주지 않는 것을 알 수 있었다. 본 연구를 통해 생활주변방사선안전관리법에서 제시된 각 항목들은 ICRP에서 제시한 방사선작업종사자의 연간 유 효선량 기준에는 크게 미치지 않았다. 하지만 일반인의 연간 유효선량보다는 약 2~3배 정도 높은 선량인 것을 알 수 있었다. 이를 통해 아직 시행 초기 단계인 생활주변방사선안전관리법에 대한 지속적인 연구와 관심이 필요한 것으로 사료된다.