• 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.

• Asian Pacific Journal of Cancer Prevention
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• 제14권11호
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• pp.6301-6304
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• 2013

Background: Some epidemiological studies reported that sunlight exposure and highvitamin D levels may decrease the morbidity and mortality related to cancer. We aimed to evaluate whether sunlight exposure has an impact on survival in patients with non small cell lung cancer. Materials and Methods: A total of 546 patients with NSCLC from two different regions (Kayseri and Adana) differing according to sunlight exposure were analysed retrospectively. Results: The median overall survival (OS) rates were 11. 6 (CI: 9.50-13.6) and 15.6 months (CI: 12.4-18.8) for Kayseri and Adana, respectively, in all patients (p=0.880). Conclusions: There were no differences between groups in terms of OS. While there is strong evidence regarding inverse relationship between cancer incidence and sunlight exposure, it is still controversial whether sunlight exposure is a good prognostic factor for survival in patients with lung cancer.

• Journal of Radiation Protection and Research
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• 제7권1호
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• pp.1-10
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• 1982

표준한국인(標準韓國人)의 체위(體位)와 내(內).외부(外部) 피폭선량(被曝線量)을 추정(推定)하기 위하여 한국인(韓國人)의 신장(身長), 체중(體重), 체표면적(體表面積)을 포함(包含)한 체위(體位)와 음식물섭취량(飮食物攝取量) 방사능물질섭취량(放射能物質攝取量) 그리고 환경방사능(環境放射能)에 의한 피폭선량(被曝線量)을 조사분석(調査分析)하여 다음과 같은 결론(結論)을 얻었다. 1) 표준한국인(標準韓國人)의 년령군(年齡群)은 남녀(男女) 모두 $20{\sim}30$세(歲)이며 남자(男子)에 있어서의 신장(身長)은 167cm, 체중(體重)은 61kg, 체표면적(體表面積)은 $1.67m^2$다. 그리고 여자(女子)에 있어서의 신장(身長)은 155cm, 체중(體重)은 51kg, 체표면적(體表面積)은 $1.51m^2$이다. 2) 한국인(韓國人) 성인(成人)은 1인(人) 1일(日) 812.8g(식물성((植物性) 669.6g, 동물성(動物性) 143.2g)의 음식물(飮食物)을 섭취(攝取)한다. 3) 한국인(韓國人) 성인(成人)은 음식물(飮食物)을 통(通)하여 1인(人) 1일(日) 약(約) 1,200pCi(${\beta}$-선(線))의 방사능물질(放射能物質)을 섭취(攝取)한다. 4) 한국인(韓國人) 성인(成人)은 년간(年間) 127mrem의 외부피폭(外部被曝)과, 8mrem의 내부피폭(內部被曝)으로 약(約) 135mrem의 환경방방선(環境放放線)에 피폭(被曝)되는 것으로 추산(推算)되나 이 선량치(線量値)는 앞으로 더 많은 자료(資料)가 보완(補完)됨에 따라 수정(修正)된다고 본다.

• Journal of Radiation Protection and Research
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• 제19권3호
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• pp.209-221
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• 1994

원자력발전소의 중대 사고시 대기로 방출된 방사성물질에 의해 피폭자가 사고후 일생동안 받게 될 전신 피폭선량과 핵종의 상대적 중요도를 방출점으로부터 거리에 따라 각 피폭경로에 대해 평가하였다. 방사능운과 지표에 침적된 방사성물질에 의한 외부피폭, 호흡과 오염된 음식물섭취에 의한 내부피폭이 피폭경로로 고려되었다. 오염된 음식물섭취에 의한 영향은 우리나라 환경을 고려하여 개발된 동적 삽식경로모델 KORFOOD을 사용하여 침적시점과 침적후 시간에 따른 음식물내 방사성물질의 농도 변화를 고려하였다. 방출점으로부터 80km까지 피폭선량을 평가한 결과, 오염된 음식물섭취에 의한 영향이 가장 높았다. 핵종별 기여도는 방사능운에 의한 외부피폭과 호흡에 의한 내부피폭의 경우 I, 침적된 방사성물질에 의한 외부피폭의 경우 Cs에 의한 영향이 가장 높았다. 오염된 음식물섭취에 의한 내부피폭의 경우 Cs은 여름철 침적, Sr은 겨울철 침적에 보다 중요한 영향을 미쳤다.

• 방사선산업학회지
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• 제18권1호
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• pp.35-42
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• 2024

Demand for RW transportation is expected to increase due to the continuous generation of RW from nuclear power plants and facilities, decommissioning of plants, and saturation of spent fuel temporary storage facilities. The locational aspect of plants and radiation protection optimization for the public have led to an increasing demand for maritime transportation, necessitating to apprehend the overseas and domestic current status. Given the potential long-term radiological impact on the public in the event of a sinking accident, a pre-transportation exposure assessment is necessary. The objective of this study is to investigate the overseas and domestic RW maritime transportation current status and overseas dose assessment cases for the public in sinking accident. Selected countries, including Japan, UK, Sweden, and Korea, were examined for transport cases, Japan and the U.S were chosen for dose assessment case in sinking accidents. As a result of the maritime transportation case analysis, it was performed between nuclear power plants and reprocessing facilities, from plants to disposal or intermediate storage facilities. HLW and MOX fuel were transported using INF 3 shipments, and all transports were performed low speed of 13 kn or less. As a result of the dose assessment for the public in sinking accident, japan conducted an assessment for the sinking of spent fuel and vitrified HLW, and the U.S conducted for the sinking of spent fuel. Both countries considered external exposure through swimming and working at seashore, and internal exposure through seafood ingestion as exposure pathway. Additionally, Japan considered external exposure through working on board and fishing, and the U.S considered internal exposure through spray inhalation and desalinized water and salt ingestion. Internal exposure through seafood ingestion had the largest dose contribution. The average public exposure dose was 20 years after the sinking, 0.04 mSv yr^-1 for spent fuel and 5 years after the sinking, 0.03 mSv yr^-1 for vitrified HLW in Japan. In the U.S, it was 1.81 mSv yr^-1 5 years after the sinking of spent fuel. The results of this study will be used as fundamental data for maritime transportation of domestic RW in the future.

• Asian Pacific Journal of Cancer Prevention
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• 제15권10호
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• pp.4165-4168
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• 2014

Background: The prognosis of primary glioblastoma (GBM) is poor. Approximately 2/3 of primary brain tumor diagnoses are GBM, of which 95% are primary lesions. In this study, we aimed to evaluate whether more sunlight exposure has an effect on survival of patients with primary GBM. Materials and Methods: A total of 111 patients with primary GBM were enrolled from Kayseri in inner Anatolia which has a cold climate (n: 40) and Mersin in Mediterranean region with a warm climate and more sunlight exposure (n: 71). The patients with primary GBM were divided into two groups as Kayseri and Mersin and compared for progression free survival (PFS) and overall survival (OS).Results: The PFS values were 7.0 and 4.7 months for Kayseri and Mersin groups, respectively (p=0.10) and the repsective OS values were 13.3 and 9.4 months (p=0.13). We did not found any significant difference regarding age, sex, comorbidity, smoking, surgery, resurgery, adjuvant chemoradiotherapy and palliative chemotherapy between the groups. Conclusions: We found that more sunlight exposure had no impact on prognosis of patients with primary GBM, adding inconsistency to the literature about the relationship between sunlight and GBM.

• 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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• 제52권8호
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• pp.1826-1833
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• 2020

Administration of stable iodine has been considered a best measure to protect the thyroid from internal irradiation by radioiodine intake, and its efficacy on thyroid protection has been quantitatively evaluated in several simulation studies on the basis of simple iodine biokinetic models (i.e., three-compartment model). However, the new iodine biokinetic model adopted by the International Commission on Radiological Protection interprets and expresses the thyroid blocking phenomenon differently. Therefore, in this study, the new model was analyzed in terms of thyroid blocking and implemented to reassess the protective effects and to produce dosimetric data. The biokinetic model calculation was performed using computation modules developed by authors, and the results were compared with those of experimental data and prior simulation studies. The new model predicted protective effects that were generally consistent with those of experimental data, except for those in the range of stable iodine administration -72 h before radioiodine exposure. Additionally, the dosimetric data calculated in this study demonstrates a critical limitation of the three-compartment model in predicting bioassay functions, and indicated that dose assessment 1 d after exposure would result in a similar dose estimate irrespective of the administration time of stable iodine.

• Journal of Radiation Protection and Research
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• 제34권3호
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• pp.121-128
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• 2009

국내 원전의 계획예방정비기간중에 원자로계통의 개방과정에서 원자로건물내 공기 중으로 누설된 $^{131}I$의 채내 흡입으로 원전 종사자의 내부피폭이 발생하였다. 이에 따라 원전에서 보유하고 있는 전신계측기(Whole Body Counter)를 이용하여 방사선작업 종료 후 즉시 원전종사자의 체내에 침적된 내부방사능을 측정하였고, 수일 경과 후 재측정하였다. 이러한 전신계측결과를 이용한 섭취량 산정 값을 원전종사자가 출입한 원자로 건물 내 공기 중의 $^{131}I$ 방사능 농도 측정결과와 원자로건물 출입기록에 근거하여 계산된 $^{131}I$ 채내 섭취량과 비교 평가하였다. 그 결과 전신계측기를 이용한 채내 방사능측정 결과와 공기중 농도를 이용한 섭취량 산정 결과는 비교적 잘 일치하는 것으로 평가되였다.

• 방사선산업학회지
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• 제17권4호
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• pp.509-518
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• 2023

The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during the dismantling process. For the disposal of Very-low-level waste, which is expected to account for the largest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detailed design to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is being developed to efficiently dispose of metal and concrete waste, which are mainly generated as Very low-level waste of decommissioning. In this study, based on the design characteristics of the 3-phase landfill disposal facility and the large container under development, radiation exposure dose evaluation was performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using the MCNP computer program, and the internal and external exposure dose evaluation due to damage to the decommissioning waste package during a drop accident was performed based on the evaluation method of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determine whether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of the evaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limit was confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the large container for dismantled radioactive waste, which is currently under development, was confirmed.