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      • KCI등재

        선진 핵연료주기 기술 개발을 위한 핵연료주기 분석 기술

        박병흥,고원일,Park, Byung-Heung,Ko, Won-Il 한국방사성폐기물학회 2011 방사성폐기물학회지 Vol.9 No.4

        핵연료주기 분석 연구는 핵연료주기 단계에서 기술들을 분석하고 요건들을 도출하여 국가적 핵연료주기 정책 설정 및 추진을 체계적으로 수행하기 위한 연구이다. 시스템 분석 기술은 대상 시스템의 비교 분석 평가에 활용되며 핵연료주기를 대상으로 하는 경우 각 국가 또는 관심 범위에 따라 다양한 방법이 사용된다. 본 연구에서는 국내 선진 핵연료주기 개발을 위해 필요한 핵연료주기 분석 전략과 함께 이를 위해 사용될 수 있는 분석 기술들을 제시하였다. 핵연료주기 분석은 전략적으로 기술적 분석, 국내외 이해관계, 국가 에너지 프로그램과 연계되어야 한다. 이를 위해 다양한 핵연료주기를 비교하여 제시된 평가 지표에 따라 분석하는 연구는 트레이드 연구 방법을 적용하여 수행할 수 있다. 본 연구를 통한 조사 분석 결과 핵연료주기 분석 전략과 함께 방법적 측면에서 트레이드 연구가 선진 핵연료주기 도출에 활용될 수 있을 것으로 파악되었다. 트레이드 연구에 필수적인 평가지표를 선정하고 각 지표별 핵연료주기에 대한 정보를 얻기 위해서는 기술성숙도 분석 방법과 핵연료주기 시뮬레이터를 활용할 수 있을 것으로 제시하였다. 이들은 핵연료주기의 기술성, 경제성, 환경영향성 등을 비교 평가하여 기술개발을 위한 방향을 제시하고 체계적인 선진 핵연료주기 도출 및 실현에 기여할 것이다. The nuclear fuel cycle (NFC) analysis is a study to set a NFC policy and to promote systematic researches by analyzing technologies and deriving requirements at each stage of a fuel cycle. System analysis techniques are utilized for comparative analysis and assessment of options on a considered system. In case that NFC is taken into consideration various methods of the system analysis techniques could be applied depending on the range of an interest. This study presented NFC analysis strategies for the development of a domestic advanced NFC and analysis techniques applicable to different phases of the analysis. Strategically, NFC analysis necessitates the linkage with technology analyses, domestic and international interests, and a national energy program. In this respect, a trade-off study is readily applicable since it includes various aspects on NFC as metrics and then analyzes the considered NFC options according to the derived metrics. In this study, the trade-off study was identified as a method for NFC analysis with the derived strategies and it was expected to be used for development of an advanced NFC. A technology readiness level (TRL) method and NFC simulation codes could be utilized to obtain the required metrics and data for assessment in the trade-off study. The methodologies would guide a direction of technology development by comparing and assessing technological, economical, environmental, and other aspects on the alternatives. Consequently, they would contribute for systematic development and deployment of an appropriate advanced NFC.

      • KCI등재

        방사성 폐기물 처리를 위한 이온성 액체 활용

        박병흥,Park, Byung Heung 한국방사성폐기물학회 2014 방사성폐기물학회지 Vol.12 No.1

        이온성 액체 기술에서의 학문적 연구들은 원자력 산업으로 확대되어 왔으며 많은 연구자들에 의해 방사성 물질의 처리에 이온성 액체의 활용이 연구되어 왔다. 다수의 연구들에 의해 사용 후 핵연료에 포함되어 있는 금속 원소들의 분광학적, 전기화학적 거동에 대한 흥미로운 결과들이 보고되었다. TBP(tri-butyl phosphate)를 용해시킨 이온성 액체에서 측정되고 관찰된 금속 이온들의 물성들은 전통적인 수용성 공정에 대한 대안 기술 개발을 유발시켰다. 한편, 수용성 및 비수용성 공정에서의 활용을 위해 이온성 액체에서 금속 이온의 전기화학적 전착이 연구되었다. 본 연구에서는 이온성 액체 연구에서 주목할 만한 내용들을 분류하고 정리하여 핵연료주기에서 이온성 액체의 활용에 대해 고찰하였다. Academic interests in ionic liquid (IL) technologies have been extended to the nuclear industry and the applicability of ionic liquids for processing radioactive materials have been investigated by many researchers. A number of studies have reported interesting results with respect to the spectroscopic and electrochemical behaviors of metal elements included in spent nuclear fuels. The measured and observed properties of metal ions in TBP(tri-butyl phosphate) dissolved ILs have led the development of alternative technologies to traditional aqueous processes. On the other hand, the electrochemical deposition of metal ions in ILs have been investigated for the application of the solvents to aqueous as well as to non-aqueous processes. In this work, a review on the application of ILs in nuclear fuel cycle is presented for the purpose of categorizing and summarizing the notable researches on ILs.

      • KCI등재

        전해환원 공정의 우라늄 산화물 환원 거동 모사를 위한 Phase-Field 이론 적용

        박병흥,정상문,Park, Byung Heung,Jeong, Sang Mun 한국방사성폐기물학회 2018 방사성폐기물학회지 Vol.16 No.3

        Under a pyro-processing concept, an electrolytic reduction process has been developed to reduce uranium oxide in molten salt by electrochemical means as a part of spent fuel treatment process development. Accordingly, a model based on electrochemical theory is required to design a reactor for the electrolytic reduction process. In this study, a 1D model based on the phase-field theory, which explains phase separation behaviors was developed to simulate electrolytic reduction of uranium oxide. By adopting parameters for diffusion of oxygen elements in a pellet and electrochemical reaction rate at the surface of the pellet, the model described the behavior of inward reduction well and revealed that the current depends on the internal diffusion of the oxygen element. The model for the electrolytic reduction is expected to be used to determine the optimum conditions for large scale reactor design. It is also expected that the model will be applied to simulate the integration of pyro-processing.

      • 폐기물 재활용을 위한 사용후핵연료 처리기술

        박병흥,김기섭,Park, Byung Heung,Kim, Ki-Sub 한국교통대학교 융복합기술연구소 2012 융ㆍ복합기술연구소 논문집 Vol.2 No.1

        Spent fuels are discharged from nuclear reactors as a result of power generations. The spent fuels would be considered as a useful resources because the main constituent is uranium and some other actinides are included in them. In order to utilize the resources chemical processes should be developed to treat the spent fuels and obtain uranium and other actinides to be fueled in a fast reactor. The technologies are categorized into wet and dry processes. In this study, the current status of such technologies is summarized to give a insight and a deep understanding on nuclear fuel cycles.

      • SCOPUSKCI등재

        열화학 황-요오드 수소 생산 공정의 요오드 결정화기 설계를 위한 결정 침강 모델링

        박병흥 ( Byung Heung Park ),정성욱 ( Seong Uk Jeong ),강정원 ( Jeong Won Kang ) 한국화학공학회 2014 Korean Chemical Engineering Research(HWAHAK KONGHA Vol.52 No.6

        SI process is a thermochemical process producing hydrogen by decomposing water while recycling sulfur and iodine. Various technologies have been developed to improve the efficiency on Section III of SI process, where iodine is separated and recycled. EED(electro-electrodialysis) could increase the efficiency of Section III without additional chemical compounds but a substantial amount of I2 from a process stream is loaded on EED. In order to reduce the load, a crystallization technology prior to EED is considered as an I2 removal process. In this work, I2 particle sinking behavior was modeled to secure basic data for designing an I2 crystallizer applied to I2-saturated HIx solutions. The composition of HIx solution was determined by thermodynamic UVa model and correlation equations and pure properties were used to evaluate the solution properties. A multiphysics computational tool was utilized to calculate particle sinking velocity changes with respect to I2 particle radius and temperature. The terminal velocity of an I2 particle was estimated around 0.5 m/s under considered radius (1.0 to 2.5 mm) and temperature (10 to 50 ℃) ranges and it was analyzed that the velocity is more dependent on the solution density than the solution viscosity.

      • SCOPUSKCI등재

        휘발산화 공정 조건에 따른 Cs-Te-O 시스템의 산화 환원 거동 연구

        박병흥 ( Byung Heung Park ) 한국화학공학회 2013 Korean Chemical Engineering Research(HWAHAK KONGHA Vol.51 No.6

        Pyroprocessing has been developed for the purpose of resolving the current spent nuclear fuel management issue and enhancing the recycle of valuable resources. Pyroprocessing has been developed with the dry technologies which are performed under high temperature conditions excluding any aqueous processes. Pyro-processes which are based on the electrochemical principles require pretreatment processes and a voloxidation process is considered as a pretreatment step for an electrolytic reduction process. Various kinds of gas conditions are applicable to the voloxidation process and the understanding of Cs behavior during the process is of importance for the analyses of waste characteristics and heat load on the overall pyroprocessing. In this study, the changes of chemical compounds with the gas conditions were calculated by analyzing gas-solid reaction behavior based on the chemical equilibria on a Cs-Te-O system. Cs2TeO3 and Cs2TeO4 were selected after a Tpp diagram analysis and it was confirmed that they are relatively stable under oxidizing atmospheres while it was shown that Cs and Te would be removed by volatilization under reducing atmosphere at a high temperature. This work provided basic data for predicting Cs behavior during the voloxidation process at which compounds are chemically distributed as the first stage in the pyroprocessing and it is expected that the results would be used for setting up material balances and related purposes.

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