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        검색결과 1,679

        141.
        2023.05 구독 인증기관·개인회원 무료
        The US NRC developed a program called NRCDose3 to evaluates the environmental impact of radiation around nuclear facilities. The NRCDose3 code is a software suite that integrates the functionality of three individual LADTAP II, GASPAR II, and XOQDOQ Fortran codes that were developed by the NRC in the 1980’s and have been in use by the nuclear industry and the NRC staff for assessments of liquid effluent and gaseous effluent, and meteorological transport and dispersion, respectively. Through the integrated program, it is possible to conduct safety assessment and environmental impact assessment from liquid and gaseous effluent when operating permits are granted. In addition to a more user-friendly graphic user interface (GUI) for inputting data, significant changes have been made to the data management and operation to support expanded capabilities. The basic calculation methods of the LADTAP II, GASPAR II, and XOQDOQ have not been changed with this update to the NRCDose3 code. Several features have been added. The previous program used only ICRP-2 dose conversion factor, but the new program can additionally use dose conversion factor of ICRP-30 and ICRP-72. In the previous program, 4 age groups (infant, child, teen, and adult) were evaluated during dose evaluation, but when ICRP-72 was selected, 6 age groups (infant, 1-year, 5-year, 10-year, 15-year, and adult) could be evaluated. In addition, when selecting ICRP-72, many user-modifiable parameters such as food intake and exposure time were added. It will be referred to E-DOSE60, a program currently under development.
        142.
        2023.05 구독 인증기관·개인회원 무료
        After the Fukushima nuclear power plant accident in 2011, interest in technology for evaluating residents’ exposure to effluents generated from nuclear power plants at the time of the accident has increased. KHNP has developed the S-REDAP program and is using it to evaluate radiation dose and recommend resident protection measures in the event of a nuclear power plant emergency. Its main functions are source term evaluation, atmospheric diffusion evaluation, radiation dose evaluation, etc. Based on these evaluations, resident protection measures are evaluated. In Japan, evaluation is conducted through a program called SPEEDI-MP (System for Prediction of Environmental Emergency Dose Information Multi-model Package) created by JAEA (Japan Atomic Energy Agency). Similar to S-REDAP, the program also evaluates effluents emitted from nuclear facilities through source term evaluation and atmospheric diffusion factor evaluation. In JAEA, through a program using SPEEDI-MP, the source term evaluation was performed in collaboration with NSC (Nuclear Safety Commission) in the event of the Fukushima nuclear plant accident, and dose evaluation in Japan was performed 2 months as an atmospheric diffusion factor using meteorological data for 2 days. Through comparative analysis of evaluation data from Japan, improvements to the current program be derived.
        143.
        2023.05 구독 인증기관·개인회원 무료
        K-DOSE60, a off-site dose calculation program currently used by khnp, is performing evaluation based on the gaseous effluent evaluation methodology of NRC Reg. Guide 1.109. In particular, H-3 and C-14, which are the major nuclides of gaseous effluent, are evaluated using a ratio activity model. Among them, H-3 is additionally evaluating the dose to OBT (Organically Bound Tritium) and HT as well as HTO (Triated water). However, NRC Reg. Guide 1.109 is a methodology developed in the 1970s, and verification was performed by applying the evaluation methodology of H-3 and C-13 presented by IAEA TRS-472 in 2010 to the current K-DOSE60. The IAEA TRS-472 methodology also includes OBT and HT for H-3. In order to apply the ratio radioactivity model presented in IAEA TRS-472, the absolute and relative humidity were calculated using the weather tower of the nuclear site and used for H-3 evaluation. For the dose evaluation of HT, the previously used Canada Chalk River Lab. (CNL) conversion factor was used. For atmospheric carbon concentration, the carbon concentration presented in IAEA TRS-472 was used, not the carbon concentration in the 1970s of NRC Reg. Guide 1.109. It was confirmed that the K-DOSE60, which applied the changed input data and methodology, was satisfied by performing comparative verification with the numerical calculation value.
        144.
        2023.05 구독 인증기관·개인회원 무료
        In 2022 and 2023, the Korea Institute of Nuclear Safety (KINS), a regulatory body, revised the regulatory guidelines for off-site dose evaluation to residents, marine characteristics surveys around nuclear facilities, and environmental radiation surveys and evaluation around nuclear facilities. In addition, the NRC, a US regulatory body, has revised regulatory guide 1.21 (MEASURING, EVALUATING, AND REPORTING RADIOACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS AND SOLID WASTE) to change environmental programs for nuclear facilities. The domestic regulatory guidelines were revised and added to reflect the experience of site dose evaluation for multiple units during the operation license review of nuclear facilities, the resident exposure dose age group was modified to conform to ICRP-72, and the environmental monitoring plan was clarified. In the case of the US, the recommended guidelines for updating the long-term average atmospheric diffusion factor and deposition factor, the clarification of the I-131 environmental monitoring guidelines for drinking water, and the clarification of the procedures described in the technical guidelines when changing environmental programs have been revised and added. Through such regulatory trend review, it is necessary to preemptively respond to changes in the regulatory environment in the future.
        145.
        2023.05 구독 인증기관·개인회원 무료
        Currently, there are 25 nuclear power plants (NPPs) in operation in Korea, including 22 pressurized water reactors (PWRs) and three pressurized heavy water reactors (PHWRs). Two NPPs, including Kori Unit 1 and Wolsong Unit 1, are permanently shut down and awaiting decommissioning. If Kori Unit 2, which is expected to be permanently shut down soon, is included, the number of decommissioning NPPs will be increased to three. Spent fuels (SFs) are continuously generated during the NPP operation, which are stored in an SF storage pool in NPPs to cool down the decay heat emitted from SFs. For safe NPP operation, SFs must be regarded as waste, and a disposal site must be selected to isolate SFs. However, an appropriate site has yet to be selected in Korea. SFs contain long-lived nuclides with a high specific activity. For disposal, it is important to characterize the nuclides in the fuels and delay the migration of the nuclides to the environment when SFs are placed in a future disposal facility. If the disposal container is broken, the nuclides in the fuels escape from the filling material, such as bentonite. These escaped nuclides are dissolved in groundwater and migrate to the surface of the earth. Thus, it is possible to assess the radiological impact, such as the exposure dose during and after the disposal, if the types and characteristics of nuclides in SFs are known. This study investigated the nuclides in SFs and identified exposure scenarios that may occur in the disposal process of SFs and migration characteristics when the nuclides leak into groundwater to propose a dose assessment methodology for workers and the public.
        146.
        2023.05 구독 인증기관·개인회원 무료
        The design of a radioactive waste disposal system should include both natural and engineered barriers to prevent radionuclide leakage and groundwater contamination. Colloids and gases can accelerate the movement of radionuclides and affect their behavior. It is important to consider these factors in the long-term stability evaluation of a deep geological repository. An experimental setup was designed to observe the acceleration of nuclide behavior caused by gas-mediated transport in a simulated high temperature and pressure environment, similar to a deep disposal repository. The study used specimens to simulate gas flow in engineered barriers, based on conditions 1000 years after repository closure. In the experiment, bentonite WRK with a dry density of 1.61 g/cm3 was used after compaction. Measurements were taken of the saturation time and gas permeability of compacted bentonite. In this study, gas was injected into saturated buffer materials at various pressures to evaluate the penetration phenomenon of the buffer material according to the gas pressure. It was observed that gas penetrated the buffer material and moved upward in the form of gas bubbles at a specific pressure. Furthermore, when a flow was continuously induced to penetrate the buffer material, erosion occurred, and the eroded particles were found to be able to float upward or be transported by gas bubbles. In future studies, analysis will be conducted on the transport rate of fine particles according to the size of gas bubbles and the characteristics of the nuclides adsorbed on the fine particles.
        147.
        2023.05 구독 인증기관·개인회원 무료
        Concrete structures of spent nuclear fuel interim storage facility should maintain their ability to shield and structural integrity during normal, off-normal and accident conditions. The concrete structures may deteriorate if the interim storage facility operates for more than several decades. Even if deterioration occurs, the concrete structures must maintain their own functions such as radiation shielding protection and structural integrity. Therefore, it is necessary to establish an analysis methodology that can evaluate whether the deteriorated concrete structure maintains its integrity under not only normal or off-normal condition but also accident condition. In accident conditions such as tip over and aircraft collision, both static material properties and dynamic properties are needed to evaluate the structural integrity of the concrete structures. Especially, it has been known to be difficult to estimate the resulted damage precisely where an aircraft collides with the degraded concrete structures at a high strain rate. In this study, damage evaluation of concrete overpack due to aircraft collisions was conducted. First, in order to verify the impact analysis methodology, the aircraft impact analysis of plane concrete overpack was performed and compared with the test results previously conducted by our research team. Then, the impact analysis for the overpack of KORAD21C was performed. In the future, the radiation shielding analysis will be performed under the conditions to evaluate whether or not the radiation shielding ability is maintained.
        148.
        2023.05 KCI 등재 구독 인증기관 무료, 개인회원 유료
        본 연구는 ‘국가 경제에 큰 영향을 미치는 중소기업들의 경쟁우위 강화와 성과 창출을 위해 어떠한 무형자원이 중요할까? 특히, 시장 환경 변화가 크고, 위기·재난 상황일 경우에는 어떤 역량이 필요할까? 시장 환경 변화가 클 때, 중소기업 중 플랫폼기업과 일반 기업의 기업성과에 미치는 역량은 다를 수 있지 않을까?’라는 질문에서 시작되었다. 이를 위해 중소기업의 경쟁우위와 성과에 영향을 미치는 주요 역량으로 기업가지향성, 흡수역량, 조직회복탄력성을 제시하였고, 특히, 최근 기업의 핵심역량으로 부상하고 있는 조직회복탄력 성이 기업성과에 어떠한 조절효과를 갖는지 실증하였다. 또한, 플랫폼기업과 일반기업을 비교하여 기업성과에 미치는 조직회복탄력성의 조절효과를 분석하였으며, 조직회복탄력성의 어떤 하위요소에 따라 조절효과가 달라지는지 실증하였다. 연구 결과, 기업가지향성, 흡수 역량은 모두 기업성과에 유의한 정(+)의 영향을 미치며, 조직회복탄력성도 기업성과에 유의한 정(+)의 영향을 미치는 것으로 나타났다. 또한, 조직회복탄력성의 하위 구성요소인 위기준비 역량, 위기대응 역량, 변화주도 역량은 기업가지향성과 기업성과 간 관계를 유의하게 조절하고, 위기준비 역량과 변화주도 역량은 흡수역량과 기업성과 간 관계를 유의하게 조절하였다. 그리고, 기업가지향성과 기업성과 간 관계에서 위기준비 역량의 조절효과, 기업가지향성과 기업성과 간 관계에서 위기대응 역량의 조절효과는 플랫폼기업에서만 유의한 결과를 보였다. 연구 결과는 조직회복탄력성이 기업성과에 직접 영향을 줄 뿐 아니라, 기업가지향성, 흡수 역량과 상호작용하여 기업성과를 더욱 높여줄 수 있으며, 플랫폼기업과 일반기업 간 조직회복 탄력성의 조절효과가 다를 수 있음을 시사하였다. 이러한 결과는 중소기업의 경영에 실질적인 도움이 될 것으로 기대된다.
        7,000원
        149.
        2023.04 KCI 등재 구독 인증기관 무료, 개인회원 유료
        해양산업시설의 위험유해물질 배출이 미치는 사회영향을 평가하고, 기술근거배출허용기준 설정과정에서 요구되는 사회영향평 가 항목 및 방법적용에 대한 시사점을 도출하였다. 연구범위는 인천광역시에 있는 해양산업시설을 대상으로 하였다. 분석결과는 다음과 같다. 첫째, 기업 및 산업에 대한 영향은 ‘큰’ 것으로 평가되었지만, 대기업은 영업이익손실과 도산가능성, 그리고 고용손실의 영향이 적 었고, 소기업과 중기업은 영향이 큰 것으로 나타났다. 둘째, 지역사회 및 경제에 대한 영향은 ‘적은’ 것으로 평가되었으나, 직접적으로 인 과관계를 지니는 어업생산자나 지역관광종사자, 그리고 해당 지역은 그 영향이 집중되어 크게 나타날 수 있기 때문에 이에 대한 세심한 정책적 개입이 필요한 것으로 판단된다. 셋째, 기술근거배출허용기준의 설정방법에서 사회적 손실비용 및 사회적 편익산정 항목과 방법 이 유용하게 적용될 수 있는 것으로 판단된다.
        4,300원
        150.
        2023.04 KCI 등재 구독 인증기관 무료, 개인회원 유료
        본 논문의 주된 연구목적은 인구이동이 인구재분포에 미치는 영향력을 분석하기 위한 방법론적 토대를 공고히 하고, 그것을 바탕으로 우리나라 인구이동의 편향성 혹은 불균형성의 시공간적 역동성을 탐색하는 것이다. 방법론적인 측면에서, 인구이동 유효도 지수(MEI)가 순이동률(NMR)에 비해 보다 적절한 측도인 것으로 판단되었다. MEI는 NMR에 비해 측도로서의 타당도가 높으며, ‘소인구문제’로부터 상대적으로 자유롭고, 인구이동의 현재적 역동성을 파악하는데 상대적으로 유리한 것으로 평가되었다. 덧붙여 MEI는 NMR에 비해 스케일 확장성이 월등해 다중 스케일을 고려한 연구 프레임워크의 수립에 훨씬 유리한 것으로 판단되었다. MEI에 기반한 분석 프레임워크를 우리나라의 최근 25년간(1998~2022년)의 데이터에 적용하여 분석하였다. 연구 결과를 요약하면 다음과 같다. 첫째, 전역 스케일의 분석 결과, 지난 25년간 전역적 MEI 값이 대략 5~10% 안에서 변동하는 경향을 보였으며, 특정한 시계열적 패턴을 보여주었다. 둘째, 지역별 스케일 분석의 결과, MEI가 NMR에 비해 인구이동의 역동성을 파악하는데 더 적절한 도구라는 사실이 입증되었다. 셋째, 지역-특수적 스케일 분석의 결과, 특별・광역시별로 매우 독특한 인구 교환 양상의 패턴이 드러났으며, 스케일 확장성이라는 측면에서 MEI는 NMR에 비해 월등하다는 사실이 입증되었다. 넷째, 지역간 스케일의 분석 결과, 인구이동 편향성이 두드러진 플로들이 확인되었다. 본 연구에서 제시된 연구 프레임워크는 다양한 방향으로 확장될 수 있는데, 집단 개별화 연구, 다변량 기법의 적용, 보다 작은 공간단위의 연구 등이다.
        5,400원