http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
- 中文 을 입력하시려면 zhongwen을 입력하시고 space를누르시면됩니다.
- 北京 을 입력하시려면 beijing을 입력하시고 space를 누르시면 됩니다.
RISS 인기검색어
- 검색키워드
- 저자 : Juyoul Kim (검색결과 26 건)
- 무료
- 기관 내 무료
- 유료
-
Juyoul Kim,Gi Young Han 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2
Since radon was detected in mattresses of famous bed furniture brands in 2018, the nuclear safety and security commission (NSSC) announced the radiation safety management act in April 2021 to protect the public health and environment. This act stipulates the safety management of radiation that can be encountered in the natural environment such as the notification of radioactivity concentration of source materials, process by-products, the installation and operation of radioactive monitors. In this study, a model was established to predict radioactive exposure dose from radioactive materials such as radon and uranium detected in consumer products such as bed mattresses, pillows, shower, bracelets and masks in order to identify major radioactive substances that largely affect the exposure dose. A period of seven years from 2014 to 2020 was investigated for the source materials and exposure doses of consumer products containing naturally occurring radioactive materials (NORMs). We analyzed these using machine learning models such as classification and regression tree (CART), Random Forest and TreeNet. Index development and verification were performed to evaluate the predictive performance of the models. Overall, predictive performance was highest when Random Forest or TreeNet was used for each consumer product. Thoron had a great influence on the internal exposure dose of bedding, clothing and mats. Uranium had a great influence on the internal exposure dose of other consumer products except whetstones. When the number of data is very small or the missing value rate is high, it is difficult to expect accurate predictive performance even with machine learning techniques. If we significantly reduce the missing value rate of data or use the limit of detection value instead of missing values, we can build a model with more accurate predictive performance.
-
-
Review of the Linkage Between Accident Management Plan and Radiation Emergency Plan
Juyoul Kim,Hyeong-Ki Shin 한국방사성폐기물학회 2022 한국방사성폐기물학회 학술논문요약집 Vol.20 No.2
The correlation between accident management plan and radiation emergency plan of Shin-Kori Units 3 and 4 was compared and analyzed from the point of view of the adequacy of facilities, equipments, organization and manpower which are necessary for the related emergency response. It was found the equipment of accident management plan and emergency response facility of radiation emergency plan had different technical contents and scope of application, so there was no risk of mutual conflict and overlapping functions. However, since the accident impact assessment code in accident management plan and computer program of radiation emergency plan were different, it was necessary to ensure the agreement or linkage of the evaluation between them. When a radiation emergency is issued in accident management plan, the composition and mission of the accident response organization were mostly consistent with the contents of the radiation emergency plan, but some corrections and improvement items were identified. Accident management plan specified that the disaster response safety center belonged to the emergency operations facility (EOF), but the radiation emergency plan did not mention it at all. The main tasks of disaster response safety center were the movement, arrangement and connection of mobile emergency response facilities, on-site construction of other emergency response facilities, and on-site road restoration. According to the accident management plan, the movement, arrangement, and connection of mobile facilities (i.e., mobile generators, mobile pumps, multi-purpose communication relay facilities), which were considered very important for the prevention and mitigation of serious accidents, were under the supervision of the disaster response safety center. It was stipulated that the operation was carried out with the cooperation of a regular emergency organization, and that the start, operation and stop of mobile equipments were to be performed under the supervision of the emergency operation team supported by the regular emergency organization. Since this organization structure and assignment of duties could not be confirmed in radiation emergency plan, it was necessary to revise and improve the radiation emergency plan for the successful operation of mobile equipments and to link them with the accident management plan.
-
-
-
-
A Comparative Review of Radiation-induced Cancer Risk Models
Lee, Seunghee,Kim, Juyoul,Han, Seokjung The Korean Association for Radiation Protection 2017 방사선방어학회지 Vol.42 No.2
Background: With the need for a domestic level 3 probabilistic safety assessment (PSA), it is essential to develop a Korea-specific code. Health effect assessments study radiation-induced impacts; in particular, long-term health effects are evaluated in terms of cancer risk. The objective of this study was to analyze the latest cancer risk models developed by foreign organizations and to compare the methodology of how they were developed. This paper also provides suggestions regarding the development of Korean cancer risk models. Materials and Methods: A review of cancer risk models was carried out targeting the latest models: the NUREG model (1993), the BEIR VII model (2006), the UNSCEAR model (2006), the ICRP 103 model (2007), and the U.S. EPA model (2011). The methodology of how each model was developed is explained, and the cancer sites, dose and dose rate effectiveness factor (DDREF) and mathematical models are also described in the sections presenting differences among the models. Results and Discussion: The NUREG model was developed by assuming that the risk was proportional to the risk coefficient and dose, while the BEIR VII, UNSCEAR, ICRP, and U.S. EPA models were derived from epidemiological data, principally from Japanese atomic bomb survivors. The risk coefficient does not consider individual characteristics, as the values were calculated in terms of population-averaged cancer risk per unit dose. However, the models derived by epidemiological data are a function of sex, exposure age, and attained age of the exposed individual. Moreover, the methodologies can be used to apply the latest epidemiological data. Therefore, methodologies using epidemiological data should be considered first for developing a Korean cancer risk model, and the cancer sites and DDREF should also be determined based on Korea-specific studies.
-
Lee, Seunghee,Kim, Juyoul Elsevier 2017 Nuclear engineering and design Vol.313 No.-
<P><B>Abstract</B></P> <P>Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1×10<SUP>−7</SUP> mSv/yr, for both disposal options and satisfied the regulatory limit of 0.1mSv/yr. However, in the drinking well scenario, the maximum exposure dose for engineered vault type disposal facility was assessed as 2.022mSv/yr where the value exceeded the regulatory limit of 1mSv/yr. The maximum exposure dose for rock-cavern type disposal facility was calculated to be 0.634mSv/yr, whose results was relatively very close to the regulatory limit considering high uncertainty of long-term environmental conditions. It was demonstrated that DSRSs including the radionuclides of <SUP>14</SUP>C, <SUP>226</SUP>Ra and <SUP>241</SUP>Am significantly contributed to the large portion of exposure dose to the public based on the long-term safety assessment. Therefore, it was recommended that the near surface disposal of DSRSs containing <SUP>14</SUP>C, <SUP>226</SUP>Ra and <SUP>241</SUP>Am should be restricted and managed by long-term interim storage option in order to minimize their potential radiological health effects.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Post-closure safety assessment of near surface disposal facility for DSRS was performed. </LI> <LI> Engineered vault and rock-cavern type were considered for normal and well scenario. </LI> <LI> <SUP>14</SUP>C, <SUP>226</SUP>Ra, <SUP>241</SUP>Am were primary nuclides contributing large portion of exposure dose. </LI> <LI> Near surface disposal of DSRSs containing <SUP>14</SUP>C, <SUP>226</SUP>Ra and <SUP>241</SUP>Am should be restricted. </LI> </UL> </P>
-
Faith Rukundo,Juyoul Kim(김주열) 대한환경공학회 2019 대한환경공학회지 Vol.41 No.8
본 연구에서는 국내 원자력발전소의 가상 중대사고시 RASCAL 및 HYSPLIT 코드를 사용해 방사선 환경영향분석을 수행하였다. 후쿠시마 사고와 벤치마킹 분석을 통해 대기로 유출된 방사선원항이 기존의 연구결과와 동일한 크기 자릿수로 합리적인 범위 내에 있음을 입증하였다. 또한 후쿠시마 사고와 유사한 장기전원상실사고를 가정하여 신고리 3, 4호기의 노심용융에 따른 영향평가를 수행한 결과, 사고로 인해 대기환경으로 유출된 방사성물질의 양은 상당하였으며 총 방사선원항은 4.1×10<SUP>16</SUP> Bq로 평가되었다. 국내 방사능방재 규제기준은 사고후 예상 주민피폭선량이 2일에 10 mSv를 초과하면 옥내대피를, 1주일에 50 mSv를 초과하면 주민소개를 권고한다. 총유효선량당량은 신고리 원자력발전소로부터 반경 4.83 km에서 11 mSv, 1.61 km에서 50 mSv로 평가되었으며 비상시 주민보호조치가 신속히 이행되어야 하는 것으로 확인되었다. Analysis of radiological environmental consequences for hypothetical severe accidents at Korean nuclear power plants (NPPs) was performed using radiological assessment system for consequence analysis (RASCAL) and hybrid single particle Lagrangian integrated trajectory (HYSPLIT) code. Through the benchmarking study of radiological source terms released to the atmosphere in case of Fukushima Daiichi NPP (FDNPP) accident, it was proved that the results of this study would fall within a reasonable range of the same order of magnitude compared with existing research results. Assuming a long-term station blackout (LTSBO) similar to FDNPP accident, we also analyzed the potential consequences of Shin Kori units 3 and unit 4 following postulated reactor core meltdown accidents which would lead to large releases of radioactive materials to the atmospheric environment and total source terms were estimated to be 4.1×10<SUP>16</SUP> Bq. Korean regulatory standards of emergency management recommended immediate protective actions of sheltering-in-place and evacuation if the projected radiation doses to the population exceeded 10 mSv and 50 mSv in the first 2 days and 1 week after the accident, respectively. It was found that total effective dose equivalent (TEDE) ranged from 11 mSv at 4.83 km to 50 mSv at 1.61 km around Shin Kori NPPs and therefore urgent public protective actions should be implemented in case of an emergency.
-
연관 검색어 추천
이 검색어로 많이 본 자료
활용도 높은 자료
