• Nuclear Engineering and Technology
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• 제49권3호
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• pp.598-608
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• 2017

A new radiation scale is proposed. With empathy toward the vast majority of people who are not well versed in radiation and related matters, and thus suffering from misunderstanding that breeds unnecessary fear of radiation, the aim of proposing a new radiation scale, radiation index (RAIN), is to put the general public at ease with the concept of radiation. RAIN is defined in dimensionless numbers that relate any specific radiation dose to a properly defined reference level. As RAIN is expressed in plain numbers without an attached scientific unit, the public will feel comfortable with its friendly look, which in turn should help them understand radiation dose levels easily and allay their anxieties about radiation. The expanded awareness and proper understanding of radiation will empower the public to feel that they are not hopeless victims of radiation. The correspondence between RAIN and the specific accumulated dose is established. The equivalence will allow RAIN to serve as a common language of communication for the general public with which they can converse with radiation experts to discuss matters related to radiation safety, radiation diagnosis and therapy, nuclear accidents, and other related matters. Such fruitful dialogues will ultimately enhance public acceptance of radiation and associated technologies.

• International Journal of Contents
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• 제16권2호
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• pp.102-108
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• 2020

The purpose of this study was to estimate and analyze the potential radiation dose that the future visitors and the cleaning staff will be exposed to when the KRR-1 reactor is converted into a memorial hall. The radiation doses were estimated using the RESRAD-BUILD software, where case, building, receptor, shielding, and source parameters were applied as the input data. Also, the basic data for the assessment of the radiation doses were determined in an indirect manner using the data on the waste generated during the decommissioning process of the reactor. The assessment results indicate that the potential radiation dose to the visitors and the cleaning staff will be less than 1 mSv, the annual dose limit for the general public. However, if anyone for a significant period of time is close to the reactor, the overall dose will increase. The radiation dose for the future visitors and the cleaning staff was determined to be lower than the annual dose limit for the general public. Given such a risk, systematic measures, such as periodic monitoring or limiting hours, are imperative.

• Journal of Radiation Protection and Research
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• 제37권3호
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• pp.129-137
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• 2012

국제방사선방호위원회(ICRP)는 2007년 발행된 ICRP 103 권고를 통해, 행위와 개입으로 대변되는 방사선방호 지침을 각 피폭상황 별로 적용하도록 변경하여 권고하였다. 이 지침에는 계획피폭상황에서 방사선방호 최적화의 수단으로 방사선작업종사자와 일반인에 대해 선원중심의 선량제약치(dose constraint)를 설정하여 운영하도록 권고하고 있다. 이 논문에서는 계획피폭상황에서 일반인 선량제약치를 설정하는데 필요한 국내 원전의 방사성물질의 배출량과 이에 따른 주변주민의 피폭방사선량 평가 결과를 분석하였다. 이를 바탕으로 국내 원전의 동일부지 내 복수호기 원전의 운영을 고려한 선량제약치 설정 방안을 제시하였다.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.2019-2024
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• 2021

For evaluating the radiological safety of dismantled concrete, the process of disposal and recycling of the radioactive concrete generated during the dismantling of Kori Unit 1 is analyzed. Four scenarios are derived based on the analysis of the concrete recycling and disposal process, and the potential exposure to the workers and public during this process are calculated. VISIPLAN and RESRAD code are used for evaluating the dosages received by the workers and public in the following four scenarios: concrete inspection, transport of concrete by the truck driver, driving on a recycled concrete road, and public living near the landfilled concrete waste. Two worker exposure scenarios in the processing of concrete and two public exposure scenarios in recycling and disposal are considered; in all the scenarios, the exposure dose does not exceed the annual dose limit for each representative.

• 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.

• 한국방사선학회논문지
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• 제8권2호
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• pp.81-88
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• 2014

진단영상의학에서 일반영상촬영의 경우 각각의 부위를 연속(series)촬영으로 검사하는 경우가 대부분이다. 그러나 환자선량권고량(DRL)의 경우 각 부위의 전후(AP)방향과 측면(lateral)자세의 촬영 측정값만이 설정되어있는 것이 현실이다. 병원에서는 환자의 연속 촬영에 의해 누적 선량이 발생되며, 이는 환자선량권고량(DRL)과 누적된 피폭선량을 비교할 수 없거나, 과소평가할 수 있다. 본 연구에서 각 부위별 연속촬영의 누적선량을 측정한 결과, 조사야에 포함된 경우 입사표면선량(ESD)을 유효선량으로 변환하면 공중의 선량한도(Individual dose)의 최대 38.06%에서 최소 0.23%까지 측정되었다. 그리고 조사야에 포함되지 않은 각 부위의 입사표면선량(ESD)을 유효선량(Effective dose)으로 변환한 경우 공중의 선량한도(Individual dose)의 최대 5%에서 최소 0.04%까지 측정되었다. 연구결과 각 부위별 연속촬영에서 입사표면선량(ESD)이 많이 증가하는 것을 알 수 있다. 따라서 병원에서는 환자선량권고량(DRL)을 구체적으로 설정할 필요가 있으며, 불필요한 검사를 줄이기 위해 환자 촬영 order의 세분화가 필요하다고 판단된다. 또한, 여러 부위의 검사에서는 정확한 조사야의 필요성이 강조된다.

• Asian Pacific Journal of Cancer Prevention
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• 제17권3호
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• pp.1197-1199
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• 2016

Background: This study aimed to facilitate decision-making in cases of breast cancer radiotherapy shifts by simulating millimetric shifts and analyzing their effects on dose distribution. Methods: The study included 30 patients with left side breast cancer who were treated with three dimensional conformal radiotherapy (3D-CRT) in the Radiation Oncology Department in Hatay Public Hospital, between January 2013 and April 2015. A treatment plan shifting at three axes with six different measures was simulated. Results: The biggest difference in values was (+3mm shift) 476cGy, with a 7.7 % change for heart and 25.6% for spinal cord. The shifts in values respectively for CTV min, mean, max were -4.8%, 2.5%, 4%. The differences for lymphatic min, mean, max were 21.3%, 20.3%, -12.2%. Conclusion: The most important thing is not the treatment plan quality, but its practicality. The treatment plan must be practical and its practice must be controlled rigidly.

• Toxicological Research
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• 제2권2호
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• pp.79-87
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• 1986

Water extracts of 21 traditional Korean herbal drugs were prepared, and a dose range of 100 mg/kg to 400 mg/kg was administered orally into mice once a day for five days. Changes of serum enzyme activities of glutamic oxaloacetic transaminase (GOT), glutamic pyruvic transaminase (GPT), blood urea nitrogen (BUN), alkaline phosphatase, body weight changes and histo pathological examination of various organs were investigated. Water extract of Ephedra Herba caused severe body weight loss at a dose of 100 mg/kg and death from a dose level of 200 mg/kg by oral administration. Angelica koreanae Radix and Anthrisci Radix showed a slight body weight loss and damages to liver and kidney.

• Journal of Radiation Protection and Research
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• 제43권2호
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• pp.39-49
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• 2018

Background: A model to assess the activity concentration of agricultural products and the public ingestion dose as result of a nuclear accident is necessarily required to manage the contaminated agricultural systems by the accident, or to estimate the effects of chronic exposure due to food ingestion at a Level 3 PSA. Materials and Methods: A dynamic compartment model, which is composed of three sub-modules, namely, an agricultural plant contamination assessment model, an animal product contamination assessment model, and an ingestion dose assessment model has been developed based on Korean farming characteristics such as the growth characteristics of rice and stockbreeding. Results and Discussion: The application study showed that the present model can predict well the characteristics of the activity concentration for agricultural products and ingestion dose depending on the deposition date. Conclusion: The present model is very useful to predict the radioactivity concentration of agricultural foodstuffs and public ingestion dose as consequence of a nuclear accident. Consequently, it is expected to be used effectively as a module for the ingestion dose calculation of the Korean agricultural contamination management system as well as the Level 3 PSA code, which is currently being developed.

• Journal of Radiation Protection and Research
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• 제35권1호
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• pp.12-20
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• 2010

원전 일차계통은 복잡한 수질환경으로 방사화생성물과 부식생성물 등 다양한 방사성핵종이 생성되고 있다. 이 방사성 핵종 중에서 원전종사자 피폭방사선량평가와 방사성유출물관리 측면에서 중요한 핵종으로는 $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;^{131}I$를 들 수 있다. 본 논문은 원전 방사선작업종사자와 원전 주변주민의 피폭방사선량에 기여가 큰 방사성핵종에 대해 살펴보고, 이들 핵종에 의한 선량평가 과정을 소개하였다. 특히 국내 원전에서 발생하였던 $^{131}I$ 내부피폭사건과 일차계통 냉각수의 탈염수 오염사건 등을 포함한 원전의 운영과정에서 일어났던 종사자와 원전주변주민에 대한 피폭 방사선량 평가 사례를 제시하였다. 또한 최근 이슈로 떠오른 삼중수소와 $^{14}C$의 선량평가에 대한 잠재적인 현안 등도 간단히 기술하였다.