• 한국방사선학회논문지
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• 제15권3호
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• pp.355-359
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• 2021

본 연구에서는 교내 실습 중 방사선(학)과 에 지정된 방사선작업종사자 및 수시출입자의 피폭 정도를 분석하여 방사선(학)과에 대한 원자력안전법의 방사선 방호에 대한 타당성과 최적화에 대한 기초 연구에 목적을 두었다. 연도별 작업종사자의 평균 피폭선량 2014년과 2016년에 0.01 mSv로 가장 낮은 수치가 나타났으며. 가장 높은 수치는 2018년도로 0.12 mSv이다. 연도별 수시출입자의 평균 피폭선량은 2018년 0.013 mSv로 가장 낮은 수치를 보였으며, 2016년 0.022 mSv로 가장 높은 수치가 나타났다. 본 연구를 통하여 방사선 발생장치만을 사용하는 대학의 담당교수, 실습 조교 및 방사선(학)과의 학생들은 교내실습 과정에서 받는 연간 피폭선량은 일반인의 선량한도인 1mSv에도 미치지 못하는 수준이다. 그러므로 방사선(학)과 학생들의 피폭선량이 일반인의 선량한도 보다 낮게 나오는 시점에서 현재 원자력안전법의 안전규제는 과도한 규제라고 판단된다. 따라서 현재의 원자력안전법에서 방사선 발생장치의 규정을 개정하거나 대학의 재학생에 대한 방사선안전관리 체계를 수정하는 것은 필요하다고 사료된다.

• 대한디지털의료영상학회논문지
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• 제12권1호
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• pp.5-8
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• 2010

Opened a court in February 10, 2006, a rule of safety management of the diagnosis radiation system was promulgated for safety of the radiation worker, patients and patients' family members. The purpose of this rule is to minimize the risk of being exposed to radiation during the process of handling X-ray. For this reason, we manufactured shielding device of mobile X-ray unit collimator for diminution of skin dose. Shielding device is made to a thickness of Pb 0.375mm. For portable chest radiography, we measured skin dose 50cm from center ray to 200cm at intervals of 20cm by Unfors Xi detector. As a result, a rule of safety management of the diagnosis radiation system has been strengthened. But there are exceptions, such as ER, OR, ICU to this rule. So shielding device could contribute to protect unnecessary radiation exposure and improve nation's health.

• Journal of Radiation Protection and Research
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• 제47권1호
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• pp.1-7
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• 2022

Background: In Japan, new regulations that revise the dose limit for the lens of the eye (hereafter the lens), operational quantities, and measurement positions for the lens dose were enforced in April 2021. Based on the international safety standards, national guidelines, the results of the Radiation Safety Research Promotion Fund of the Nuclear Regulation Authority, and other studies, the Working Group of Radiation Protection Standardization Committee, the Japan Health Physics Society (JHPS) developed a guideline for radiation dose monitoring for the lens. Materials and Methods: The Working Group of the JHPS discussed the criteria of non-uniform exposure and the management criteria set not to exceed the dose limit for the lens. Results and Discussion: In July 2020, the JHPS guideline was published. The guideline consists of three parts: main text, explanations, and 26 examples. In the questions, the corresponding answers were prepared, and specific examples were provided to enable similar cases to be addressed. Conclusion: With the development of the guideline on radiation dose monitoring of the lens, radiation managers and workers will be able to smoothly comply with revised regulations and optimize radiation protection.

• 한국방사선학회논문지
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• 제3권1호
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• pp.23-28
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• 2009

방사선동위원소 I-131을 이용한 질병의 치료는 핵의학 분야의 아주 중요한 부분을 차지하고 있다. 환자피폭에서 주의사항으로는 첫째 진료목적상 필요로 하는 선량을 초과하지 말아야 한다. 둘째 불필요한 피폭을 억제하여야 한다. 셋째 방사선을 사용하지 않고 동일한 진료목적을 달성할 수 있는지 면밀히 검토해봐야 한다. 이러한 목적을 달성하기 위해서는 환자에 대한 피폭선량의 평가가 필요하다. 본 연구에서는 치료병실 환자의 안전관리를 도모하고자 에어샘플러를 이용하여 공기를 채집하고, 채집한 시료의 방사선을 HPGe 감마카운터로 측정하였다. 치료병실에서 채집한 시료의 I-131 측정결과의 최고값은 $404.11Bq/m^3$, 평균값은 $228.27Bq/m^3$, 최저값은 $126.17Bq/m^3$ 이었다.

• Nuclear Engineering and Technology
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• 제46권4호
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• pp.467-474
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• 2014

The aim of this paper is to describe a relatively recent international agreement on the widely debated concepts of: (i) attributing effects to low dose radiation exposure situations that have occurred in the past and, (ii) inferring radiation risk to situations that are planned to occur in the future. An important global consensus has been recently achieved on these fundamental issues at the level of the highest international intergovernmental body: the General Assembly of the United Nations. The General Assembly has welcomed with appreciation a scientific report on attributing health effects to radiation exposure and inferring risks that had been prepared the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) following a formal request by the General Assembly.

• Journal of Radiation Protection and Research
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• 제34권1호
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• pp.31-36
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• 2009

일부지역의 병원에 설치, 운영되고 있는 진단용 X선 발생장치틀 의원, 병원, 종합병원별로 관 전압, 관 전류/량, 조사기간, 조사선량 성능을 평가하여 측정방법과 기술을 배우고 중요성을 알리고자 한다. 진단용 X선발생장치를 그룹별로 10대씩 총 30대에 대하여 관전류/량, 조사시간측정기를 사용하여, 백분율평균오차로 평가하였고 그에 따른 조사선량의 재현성은 변동계수를 계산하여 평가하였다. 진단용 X선 발생장치 30대 중 부적합한 장치는 관전압정확도 시험에서 5대(16.7%), 관전류정확도시험에서 3대(10,0%), 관전류량정확도 시험에서는 4대(13.3%), 조사시간정확도 시험에서는 5대(16.7%), 조사선량의 재현성 시험에서는 7대(23.3%)로 조사되었다. 진단용 X선 발생장치를 관리규정에 의거하여 성능검사 결과에 의해 성능관리의 심각성을 알 수 있었고, 이에 주기적으로 실시하여야 함은 물론 안전하게 관리함으로써 환자 및 방사선관계종사자에 대하여 방사선으로 인한 방사선 피폭경감, 화질영상관리, 재촬영 감소 둥에 의해 환자에게 양질의 의료서비스를 제공하게 될 것이다. 따라서 정기적인 성능검사가 필요하다고 사료된다.

• Nuclear Engineering and Technology
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• 제56권10호
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• pp.4384-4389
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• 2024

NORM is used as a raw material in various industries worldwide. According to the IAEA, radiological effects may occur in the environment due to raw materials and by-products generated from NORM industries. The objective of this study was to assess radiological environmental impact of the phosphate processing industry to identify the radiological effects on the general public. The resident farmer scenario was chosen as the exposure scenario due to the living characteristics of the public around the facility and the conservatism of the assessment. The RESRAD-OFFSITE code was used to evaluate the radiation dose to the public. The maximum radiation dose to the public was 6.13 × 10^-3 mSv/y. Main exposure pathways were aquatic food ingestion, radon inhalation, and meat ingestion. The uranium series accounted for about 99 % of the total radiation dose, while the thorium series and K-40 nuclides accounted for less than 1 %. These study results can be used for management of radiological impact to the public around domestic NORM industries.

• Journal of Radiation Protection and Research
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• 제45권2호
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• pp.53-68
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• 2020

Background: International organizations such as the World Health Organization (WHO) and the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) reported public exposure doses due to radionuclides released in the Fukushima nuclear accident a few years after the event. However, the reported doses were generally overestimated due to conservative assumptions such as a longer stay in deliberate areas designated for evacuation than the actual stay. After these reports had been published, more realistic dose values were reported by Japanese scientists. Materials and Methods: The present paper reviews those reports, including the most recently published articles; and summarizes estimated effective doses (external and internal) and issues related to their estimation. Results and Discussion: External dose estimation can be categorized as taking two approaches-estimation from ambient dose rate and peoples' behavior patterns-and measurements using personal dosimeters. The former approach was useful for estimating external doses in an early stage after the accident. The first 4-month doses were less than 2 mSv for most (94%) study subjects. Later on, individual doses came to be monitored by personal dosimeter measurements. On the basis of these measurements, the estimated median annual external dose was reported to be < 1 mSv in 2011 for 22 municipalities of Fukushima Prefecture. Internal dose estimation also can be categorized as taking two approaches: estimation from whole-body counting and estimation from monitoring of environmental samples such as radioactivity concentrations in food and drinking water. According to results by the former approach, committed effective dose due to ¹³⁴Cs and ¹³⁷Cs could be less than 0.1 mSv for most residents including those from evacuated areas. Conclusion: Realistic doses estimated by Japanese scientists indicated that the doses reported by WHO and UNSCEAR were generally overestimated. Average values for the first-year effective doses for residents in two affected areas (Namie Town and Iitate Village) were not likely to reach 10 mSv, the lower end of the doses estimated by WHO.

• Nuclear Engineering and Technology
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• 제51권1호
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• pp.303-309
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• 2019

Tritium is an important nuclide that must be monitored for radiation safety management. In this study, HTO was orally administered to rats at the level of 37 kBq ($1{\mu}Ci$) or 370 kBq ($10{\mu}Ci$) to examine tissue distribution and excretion levels. After sacrifice, wet and dry tissue samples were weighed and analyzed for tissue free-water tritium (TFWT) and organically bound tritium (OBT). The mean tissue concentrations of TFWT (OBT) were 30.9 (17.8) and 4.4 (8.1) Bq/g on days 7 and 13 at the 37 kBq level and 30.8 (64.6) Bq/g on day 17 at the 370 kBq level. To assess the cytogenetic damage due to tritium exposure, a cytokinesis-blocked micronucleus (MN) assay was performed in blood samples from rats exposed to HTO for 14 and 21 days after oral administration. There was no significant difference in the MN frequencies between the control and exposed rats.

• 대한방사선기술학회지:방사선기술과학
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• 제43권2호
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• pp.123-128
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• 2020

Radiation Following the 2011 Fukushima nuclear accident in Japan, public interest and anxiety about radiation safety increased, and vague anxiety about commonly exposed living radiation was generated. The Atomic Energy Safety Commission has been conducting a survey of processed products that advertise "negative ions" and "far-infrared" emissions under the Living Radiation Safety Management Act. In this study, in-depth analysis was performed from a statistical point of view using the measurement data presented in the Nuclear Safety Committee's actual survey analysis report as secondary data. As a result, there was a statistically significant difference (p<0.005) between latex and civil affairs products. There were also statistically significant differences (p<0.05) in the results of testing whether there were significant differences in the annual exposure dose between groups after categorizing 71 civil products, including radon beds, into bed, bedding, and living and other categories. The correlation analysis results also confirm that, as is commonly known, the annual doses received from processed products are associated with radon derived from U-238 and Th-232.