• 산업과 과학
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• 제2권3호
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• pp.1-7
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• 2023

최근 방사능 노출에 대한 염려에 대한 이슈가 높아지고 있다. 토양, 물, 공기, 작물등에 영향을 주며 장기적으로 환경오염 및 식량오염이 발생하며 나아가 사회적인 혼란 및 경제적 타격을 초래할 것으로 여겨진다. 방사능 노출로 질병을 일으키기도 하지만, 질병진단을 위한 방법으로, X선촬영, CT, PET-CT등 핵의학 검사를 실시하고, 암치료 목적으로 방사선 동위원소에 노출시키기도 한다. 후쿠시마 방사능 폐기물 방류소식으로 물, 특히 식수에 포함되는 방사선에 대한 헝가리의 사례 연구 및 남극 대륙의 Larsemann Hills 지역 검사에서 세계 보건 기구에서 권장하는 음용수의 규정된 방사능 한계 내에 있었다. DNA손상, 세포 및 장기손상, 암에 관련된 내용을 중심으로 방사선 보호제를 살펴보고, 또한 복구물질중 ACE억제제, 항산화제, 천연물질등에 관하여 여러 문헌을 조사하였다. 일상에서 방사능에 노출되지만 안전할 수 있는 이유는 아마도 방사선보호물질, 방사능 피폭에 대한 복구 물질이 있을 것으로 여겨, 가능한 물질들을 찾아보고자 한다.

• Journal of Radiation Protection and Research
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• 제47권4호
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• pp.204-213
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• 2022

Background: The accident at the Fukushima Daiichi nuclear power plant increased the level of anxiety related to the radioactive contamination of various foods sourced in Japan. Particularly, after the accident, the detection of artificial radionuclides in locally produced foods raised food safety concerns. In this study, the radioactivity concentrations and annual ingestions of ⁴⁰K and ¹³⁷Cs in food products commonly and frequently consumed by the general public were investigated, and the annual effective dose of each was evaluated. Materials and Methods: The 2016-2018 data from the Radiation Safety Management Report released by the Korea Nuclear Safety Technology Center was referenced for the evaluation of the amounts of ⁴⁰K and ¹³⁷Cs contained in food. Using the food-ingestion survey mentioned above as a reference, we selected 62 foods to include in our radioactivity concentration and dose assessment. We also developed a questionnaire and evaluated the responses from the subjects who answered the questionnaire. Results and Discussion: The radioactivity concentration of ¹³⁷Cs was found to be close to or below the level of minimum detectable activity. Additionally, the annual ingestion of 62 foods was 294.77 kg/yr, the effective doses from ⁴⁰K and ¹³⁷Cs were 136.4 and 0.163 μSv/yr, respectively. Conclusion: Thus, the findings confirmed that the effective dose from ⁴⁰K and ¹³⁷Cs in food tends to be lower than the effective dose limit of 1 mSv/yr suggested by the International Commission on Radiological Protection (ICRP) Publication 60. The questionnaire developed in this study is expected to be useful for estimating the annual effective dose status of Korean adults who consume foods containing ⁴⁰K and ¹³⁷Cs.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.133-140
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• 2016

Backgrounds: The accident at Fukushima Daiichi Nuclear Power Plant (NPP), March 2011, caused serious radioactive contamination over wide area in east Japan. Therefore, it is important to know the effect of the accident and the status of NPP. Materials and Methods: This paper provides a review on the status of radiation dose and radioactive contamination caused by the accident on the basis of publicized information. Results and Discussion: Monitoring of radiation dose and exposure dose of residents has been conducted extensively by the governments and various organizations. The effective dose of general residents due to the accident proved to be less than a mSv both for external and internal dose. The equivalent committed dose of thyroid was evaluated to be a few mSv in mean value and less than 50 mSv even for children. Monitoring of radioactivity concentration has been carried out on food ingredients, milk and tap water, and actual meal. These studies indicated the percentage of foods above the regulation standard was over 10% in 2011 but decreasing steadily with time. The internal dose due to foods proved to be tens of ${\mu}Sv$ and much less than that due to natural $^{40}K$ even in the Fukushima area and decreasing steadily, although high level concentration is still observed in wild plants, wild mushrooms, animals and some kind of fishes. Conclusion: According to extensive studies, not only the effect of the accident but also the pathway and countermeasures against radioactive contamination have been revealed, and they are applied very effectively for restoration of environment and reconstruction of the area.

• 대한방사선기술학회지:방사선기술과학
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• 제41권5호
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• pp.437-444
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• 2018

Whole-Body counters have been used to evaluate the internal contamination of gamma emitting radionuclides. Among the whole-body counters used in domestic nuclear facilities, Fastscan made by CANBERRA contains 2 NaI(Tl) detectors and is generally used to monitor the primary internal exposure. It has the advantage of achieving MDA even with short time measurements. Accuscan is a bed type, and has good energy resolution because it is composed of HPGe detector. Since the Accuscan with better energy resolution than Fastscan has better able to identify radionuclides, it is used to monitor secondary internal exposure. Some nuclear facilities have only Fastscan. We analyzed statistically whether Fastscan is enough to ensure accuracy and precision comparing with Accuscan. To do this, we prepared a CRM created by the Korea Research Institute of Standards and Science. We also obtained the data of 6 Fastscans and 5 Accuscans in domestic nuclear facilities. As a result of the study, although Fastscan compared with Accuscan is not as accurate as the Accuscan, the precision is statistically same. However, accuracy of Fastscan is in compliance with international standards except low energy range. In terms of accuracy and precision except radionuclides emitting low energy, it is possible to measure radioactivity inside workers even in nuclear facilities where only Fastscan is used.

• 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.

• 방사성폐기물학회지
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• 제21권2호
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• pp.255-269
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• 2023

Compared to operational wastes, nuclear power plant (NPP) decommissioning wastes are generated in larger quantities within a short time and include diverse types with a wider range of radiation characteristics. Currently used 200 L drums and IP-2 type transport containers are inefficient and restrictive in packaging and transporting decommissioning wastes. Therefore, new packaging and transport containers with greater size, loading weight, and shielding performance have been developed. When transporting radioactive materials, radiological safety should be assessed by reflecting parameters such as the type and quantity of the package, transport route, and transport environment. Thus far, safety evaluations of radioactive waste transport have mainly targeted operational wastes, that have less radioactivity and a smaller amount per transport than decommissioning wastes. Therefore, in this study, the possible radiation effects during the transport from NPP to disposal facilities were evaluated to reflect the characteristics of the newly developed containers and decommissioning wastes. According to the evaluation results, the exposure dose to transport workers, handling workers, and the public was lower than the domestic regulatory limit. In addition, all exposure dose results were confirmed, through sensitivity analysis, to satisfy the evaluation criteria even under circumstances when radioactive materials were released 100% from the container.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2606-2613
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• 2022

Spent resin often exceeds radiation limits for safe disposal, creating a need for commercial-scale treatment techniques to reduce resin radioactivity. In this study, the radiological safety of a commercialized spent resin treatment device with a treatment capacity of 1 ton/day was evaluated. The results confirm that the device is radiologically safe in the event of an accident. This device desorbs ¹⁴C from the spent resin, allowing disposal as low-level waste instead of intermediate-level waste. The device also reduces overall waste by recycling the extracted ¹⁴C. Potential accident scenarios were explored to enable dose assessments for both internal and external exposure while preventing further spillage of the device and processing the spilled resin. The scenarios involved the development of a surface fracture on the resin mixture separator and microwave systems, which were operated under pressure and temperature of 0-6 bar and 0-150 ℃, respectively. In the case of accidents with separator and microwave device, the maximum allowable working time of worker were derived, respectively, considering external and internal exposures. When wearing the respirator corresponding to APF 50, in the case of the microwave device accident scenario, the radiological safety was confirmed when the maximum worker worked within 132.1 h.

• 한국방사선학회논문지
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• 제10권7호
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• pp.489-494
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• 2016

사이클로트론에서 발생되는 핵반응은 불필요한 중성자를 발생시키며, 이로 인해 주변 물질들이 방사화되게 된다. 방사화된 물질은 방사선피폭의 원인으로, 공기가 방사화 되었을 경우 인체에 흡입되어 내부피폭을 발생 시킨다. 이에 본 연구에서는 16.5 MeV의 초소형 사이클로트론의 운영에 따른 내부 공기의 방사화를 분석하고자 하였다. 실험결과 초소형 사이클로트론의 핵반응으로 발생되는 방사화는 종사자에게 매우 낮은 내부피폭을 발생시키는 것을 확인할 수 있었으며, 방사화로 인하여 발생된 방사능을 법적 기준치와 비교하여 보았을 때 기준치 이하로 법적 관리의 대상에서 제외 될 수 있음을 알 수 있었다. 하지만, 사이클로트론의 에너지가 높아짐에 따라 내부피폭의 위험성은 더욱 높아질 우려가 있으며, 이에 따라 국내에 정립 되어 있지 않는 방사선 관련 시설의 환기설비에 대한 기준이 필요할 것으로 사료되었다.

• 실내환경 및 냄새 학회지
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• 제16권4호
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• pp.297-307
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• 2017

As radon is a naturally occurring radioactive gas that can cause lung cancer and is classified as a Group 1 carcinogen, it is essential for the public to be aware of what radon is, and how to manage radon. Therefore, general information on radon, as well as its health risks, measurement methods, mitigation methods and suggestions for its management are addressed in this article. Over the last one to two decades, a number of wide-ranging studies on radon measurement and mitigation have been conducted in Korea, and the results of each study are comparable to the research achievements of other developed countries. For this reason, it is time to systematically establish a well-made Korean radon management organization.

• 방사성폐기물학회지
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• 제5권2호
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• pp.91-101
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• 2007

본 연구에서는 원전연료 가공시설에서 발생한 콘크리트 폐기물을 자체처분 하기 위란 국내 규제요건을 검토하였고, 매립 및 재활용에 따른 작업자 및 일반인의 방사선학적 위해도를 평가하기 위해 RESRAD Ver. 6.3, RESRAD BUILD Ver. 3.3 전산코드를 사용하여 피폭선량을 평가하였다. 피폭선량 평가 결과에 따라 유도된 처분제한치는 콘크리트 폐기물 매립의 경우 0.1071Bq/g (3.5% 농축우라늄), 재활용의 경우 $0.05515Bq/cm^2$(5% 농축우라늄)이었다. 또한, 자체처분대상 콘크리트 폐기물의 제염 후 잔류방사능을 조사한 결과, 표면오염도는 전체평균이 $0.01Bq/cm^2$(알파방출체), 콘크리트 폐기물 표면에서 채취한 시료의 방사성핵종 분석결과 $^{238}U$은 0.0297Bq/g, $^{235}U$의 농축도는 2w/o 이하였고, 인위적 오염으로 예상되는 $^{238}U$의 농도는 0.0089Bq/g 이었다. 따라서, 자체처분 대상 콘크리트 폐기물의 매립 및 재활용시 일반인 및 작업자에게 미치는 방사선학적 위해도는 원자력관계법령에서 정하는 처분제한치(개인선량 $10{\mu}Sv/yr$, 집단선량 $1man{\cdot}Sv/yr$) 이하임을 확인하였다.