• 대한방사선기술학회지:방사선기술과학
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• 제41권6호
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• pp.587-594
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• 2018

The purpose of this study was to develop the indirect dosimetry by calculation (IDC) method for diagnostic X-ray equipment. The experiments were performed with inverter type X-ray tubes: Toshiba (E7252X, Japan) and Varian (RAD-14, USA). For the development method, we first applied the standard quality of X-ray beam shown in the TRS457 document, and second, to produce the constants of trendline for the IDC, the total filtration on X-ray beam was subdivided. Third, in order to increase the precision, the energy region was divided into the high energy region and the low energy region and developed by the IDC. In order to verify the IDC, mean dose (mR) values were measured for three Toshiba X-ray tubes and three Varian X-ray tubes at clinical medical institutions and then compared with the IDC on the 2013. As a result, compared with the previous study, the accuracy of the IDC of this study were improved by 2.71% and 9.91% in Toshiba and Varian X-ray tubes, respectively.

• Nuclear Engineering and Technology
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• 제32권4호
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• pp.350-360
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• 2000

In Korea, the dose limits are reduced and are set at the ICRP-60 iimits. However, derived limits tabulated as MPC in air and water are still specified in Notice No.98-12. There are some discrepancies between the primary dose limits and MPCs in air and water. Therefore, in order to accept ICRP-60 recommendations fully, derived limits such as ALI, DAC, ECL for radiological protection against ionizing radiation based on ICRP-60 recommendations were calculated using modified methods of those of 10 CFR part 20, dose limits and committed effective dose coefficients of the Basic Safety Standards of the IAEA. The derived limits in this study were also compared with those prescribed in 10 CFR part 20 as well as MPCs of Notice No. 98-12 in order to analyze the impact of implementing derived limits on nuclear facilities. ECLs in air and water for the control of radioactive discharge into the environment in this study are shown to have lower values (i.e. more conservative), for most part, than those in Notice No. 98-12. Especially, for uranium elements, ECLs in water are approximately a magnitude in the order of two lower than those in Notice No.98-12.

• Journal of Radiation Protection and Research
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• 제28권1호
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• pp.65-73
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• 2003

The paper discusses results of recent international intercomparison exercises on internal dose assessments, status of up to date internal dosimetry methods and the radiological legislation developed and implemented in Korea, European Union and Ukraine. The system of radiation protection in Korea is based on the Korean Atomic Energy Regulatory Enforcement on Safety Standards (Ministry Notice No. 2001-2). The notice is based on the recommendations in ICRP Publication 60 (1990) and IAEA Basic Safety Standards (1996). But the full implementation of the notice by the end of the year 2002 is not required because of the socio-economic situation and inexperience in internal radiation dosimetry Regulatory framework for internal radiation dosimetry is under development toward the full implementation of the notice from January 1, 2003. The system of radiation protection in Ukraine is based on the National radiation protection regulatory code NRBU-97. The code was developed and adopted in 1998 and replaced the Regulations of Former Soviet Union. The document is based on the ICRP Publication 60, Euratom Directive 96/29 and IAEA Basic Safety Standards (1996). The transitional period of 5 years (effected till January 2003) is established for implementation of all requirements of this new regulation. The system of radiation protection in the European Community is based on the Council Directive 96/29/Euratom, adopted in 1996 and enforced from 13 May 2000. Directive 96/29/Euratom has the status of the European law.

• 대한방사선기술학회지:방사선기술과학
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• 제42권3호
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• pp.195-199
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• 2019

Most of the vascular procedures performed for various diagnoses and treatments of various abdominal intervention procedures performed by the Department of Radiology and Angiography are performed by puncture of the femoral artery. For this reason, patients should undergo blood-related tests such as prothrombin time (PT) and partial thromboplatin time (PTT). Therefore, many patients are instructed to take precautions such as putting a sandbag on the puncture site to prevent delayed hemorrhage after hemostasis of the femoral artery puncture site, and not to bend the leg of the treated area for about 3 hours. Because of this, many patients have complained of pain during the procedure and inconvenience during the absolute bed rest time in the ward. The purpose of this study was to compare the safety of balloon ancillary devices with sandbags placed on the hemostasis site to prevent delayed hemorrhage after arterial puncture. We compared the safety of each patient with the results of medical records in consideration of the problem that the patient could not press with the focus, the position of the patient was changed depending on the patient's body shape, and the problem of falling down according to the location of the puncture site. As a result, the use of a balloon type ancillary device improves the effect of continuous hemostasis, reduces discomfort during the patient's absolute stabilization time, increases the patient's satisfaction, and is a good alternative to the existing sandbag.

• 방사성폐기물학회지
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• 제19권1호
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• pp.123-132
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• 2021

Radiological impact analyses were carried out for a near-surface radioactive waste repository at Gyeongju in South Korea. The RESRAD-ONSITE code was applied for the estimation of maximum exposure doses by considering various exposure pathways based on a land area of 2,500 ㎡ with a 0.15 m thick contamination zone. Typical influencing input parameters such as shield depth, shield materials' density, and shield erosion rate were examined for a sensitivity analysis. Then both residential farmer and industrial worker scenarios were used for the estimation of maximum exposure doses depending on exposure duration. The radiation dose evaluation results showed that 60Co, 137Cs, and 63Ni were major contributors to the total exposure dose compared with other radionuclides. Furthermore, the total exposure dose from ingestion (plant, meat, and milk) of the contaminated plants was more significant than those assessed for inhalation, with maximum values of 5.5×10-4 mSv·yr-1 for the plant ingestion. Thus the results of this study can be applied for determining near-surface radioactive waste repository conditions and providing quantitative analysis methods using RESRAD-ONSITE code for the safety assessment of disposing radioactive materials including decommissioning wastes to protect human health and the environment.

• 대한방사선기술학회지:방사선기술과학
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• 제36권4호
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• pp.281-290
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• 2013

이 연구는 의료기관인증 획득 당시와 인증획득 이후 인증기준 준수율이 얼마나 향상 또는 감소되었는지를 확인하고자 의료기관인증을 획득한 대전지역의 4개 대학병원에 종사하며 의료기관 인증평가를 경험한 방사선사를 대상으로 하였다. 연구방법으로는 의료기관인증평가 기준 틀을 재분류하여 환자안전, 직원 및 환경안전 영역에 대해 평가하였다. 환자안전(patient safety) 8문항, 직원안전(staff Safety) 5문항, 환경안전(environmental safety) 3문항으로 총 16문항으로 구성하였고 인증기준 준수율은 10점 척도로 인증평가 당시와 현재의 인증기준 준수율을 측정하였다. 연구결과 인증기준 준수율은 인증평가 당시에 비해 2012년 12월 현재 평균적으로 환자안전, 직원 및 환경안전 영역 모두가 떨어졌다. 세부문항 16개 중에서 가장 많이 떨어진 문항은 환자안전 영역의 손위생이었다. 손위생은 개인의 노력 및 필요성에 대한 인식도 중요하지만 지속적인 교육과 관리 감독이 역시 중요하다. 따라서 의료기관들은 인증기준 준수의 필요성에 대해 지속적인 교육 시행과 적극적인 관리 감독이 필요하다.

• 한국의학물리학회지:의학물리
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• 제25권1호
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• pp.8-14
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• 2014

의료분야에서 방사선 진료기술의 발전에 따라 방사성폐기물의 수량은 급속히 증가하고 있다. 방사성폐기물에는 주로 PET/CT에 사용하는 $^{18}F$을 비롯하여 핵의학검사에 사용하는 $^{99m}Tc$ 등과 같이 반감기가 매우 짧은 방사성동위원소가 함유되어 있다. 이를 처분하기 위하여 국제원자력기구(IAEA)는 개인선량($10{\mu}Sv/y$) 및 집단선량(1 man-Sv/y)과 핵종별 농도에 근거하여 각각 폐기물의 규제해제기준을 제시(IAEA Safety Series No 111-P-1.1, 1992 및 IAEA RS-G-1.7, 2004)하였다. 이 연구에서는 IAEA 기준에 따른 방사능농도를 측정하기 위하여, $^{18}F$, $^{99m}Tc$, $^{123}I$, $^{125}I$ 및 $^{201}TI$ 관련 방사성폐기물을 수집하고 측정용기를 준비하였다. 그리고 MCA를 이용한 감마방사능 측정, 감마계수기를 이용한 감마방사능 측정, 베타입자 방출 핵종의 방사능 측정방법 및 절차를 수립하고, 표준물질을 제작하여 교정하였다. 측정결과를 근거로 방사능 감쇠 유도식을 산출하였으며, 이를 이론식과 대비하여 고찰하였다. 이 연구 결과는 ISO 표준으로 추진할 예정이다.

• 한국방사선학회논문지
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• 제17권5호
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• pp.791-800
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• 2023

본 연구는 부산에 거주하는 시민을 대상으로 방사선 사회안전망 구축과 시민의 안전의식 및 안전 문화 정착에 대해 조사하여 방사선으로부터 안전한 사회를 조성할 수 있는 기틀을 마련하고자 수행하였다. 자료수집은 온라인 설문을 실시하고, 200부의 설문을 분석하였다. 자료는 SPSS Window Ver 28.0을 이용하여 분석하였다. 집단 간 차이 검증을 위해 t-test와 일원배치분산분석(one way ANOVA)을 실시하였으며, 변수 간의 연관성을 확인하기 위하여 상관분석을 실시하였다. 그리고 변수 간 미치는 영향을 확인하기 위하여 다중선형회귀분석(Multiple Linear Regression Analysis)을 실시하였다. 그 결과 첫째, 사회안전망 구축, 시민의 안전의식, 안전 문화 정착에서 성별은 남자, 연령은 20대, 학력은 고등학교 졸업 그룹의 점수가 높게 나타났다. 그중 성별에서 사회안전망 구축은 유의수준 .01, 안전 문화정착은 유의수준 .05에서 통계적 차이를 보였다. 직업에서는 방사선 사회안전망 구축에 대해서 전문직 종사자와 서비스직 종사자가 유의수준 .05에서 통계적 차이를 나타냈다. 둘째, 다중회귀분석 결과 방사선 사회안전망 구축의 하부요인인 '지자체 방사선 안전교육'이 시민의 안전의식과 안전 문화 정착에 정적인 영향을 끼치는 것으로 나타났다. 셋째, 사회안전망 구축과 시민의 안전의식, 안전 문화 정착 간 상관관계 분석 결과 정적 상관을 나타냈다. 따라서, 방사선 사회안전망 구축이 잘되어 있으면 시민의 안전의식과 안전문화 정착에도 긍정적인 영향을 미치는 것으로 판단된다.

• 대한방사선기술학회지:방사선기술과학
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• 제44권5호
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• pp.525-534
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• 2021

In order to provide high-quality medical services to the public and contribute to the improvement of public health, it is necessary to enact an independent law according to the work of radiological technologists. Therefore, this study intends to review the regulations related to radiographers in the Medical Service Technologists, etc. Act. and to present opinions and directions for enactment of individual laws for radiological technologists. An online survey was conducted to 15,000 radiological technologists working in medical institutions and education sites in Korea; 1,027 people (6.85%) responded. The questionnaire consisted of 3 questions on demographic characteristics, 5 questions on the scope of work, and 12 questions on the revision of the Medical Service Technologists, etc. Act. and the establishment of the Radiological Technologist Independent Act. Reliability and factor analysis were performed on 9 questions measured on a Likert 5-point scale in "Revision of the Medical Service Technologists, etc. Act. and the establishment of the Radiological echnologist Independent Act" among the questionnaire items. Reliability for the total 9 questions was Chronbach α=0.728. There was a high perception that the regulations related to radiological technologists were insufficient in the current Medical Service Technologists, etc. Act., and the perception that examinations performed by radiological technologists at medical institutions were included in medical practice was high. If the Radiological Technologist Independent Act is enforced, a high percentage of respondents said that they could receive legal protection through the institutionalization of the scope of work, that the status of radiological technologists would be improved, and the scope of work would be expanded. The response that the scope of work of radiological technologists should be included was the highest at 96.6%. In the analysis according to demographic characteristics, it was found that 96.7% of the respondents were agreed regardless of the factors. Radiological technologists will have to work hard to secure the public health by coping with new radiology devices, procedures and treatment methods. Therefore, as the results of this study, it is expected that the enactment and implementation of the Radiological Technologist Independent Act will contribute to the improvement of the quality of treatment for patients and to the public health.

• 대한방사선기술학회지:방사선기술과학
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• 제43권5호
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• pp.389-395
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• 2020

The evaluation of radioactivated components of heavy-ion accelerator facilities affects the safety of radiation management and the exposure dose for workers. and this is an important issue when predicting the disposal cost of waste during maintenance and dismantling of accelerator facilities. In this study, the FLUKA code was used to simulate the proton treatment device nozzle and classify the radio-nuclides and total radioactivity generated by each component over a short period of time. The source term was evaluated using NIST reference beam data, and the neutron flux generated for each component was calculated using the evaluated beam data. Radioactive isotopes caused by generated neutrons were compared and evaluated using nuclide information from the International Radiation Protection Association and the Korea Radioisotope association. Most of the nuclides produced form of beta rays and electron capture, and short-lived nuclides dominated. However, In the case of ⁵⁴Mn, which is a radioactive product of iron, the effect of gamma rays should be considered. In the case of tritium generated from a material with a low atomic number, it is considered that handling care should be taken due to its long half-life.