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Journal of the Nuclear Fuel Cycle and Waste Technology最新文献

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A Study on Electrochemical Behaviors of Samarium Ions in the Molten LiCl-KCl Eutectic Using Optically Transparent Electrode 用光学透明电极研究钐离子在熔融LiCl-KCl共晶中的电化学行为
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.313
A. Lee, B. Park
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引用次数: 1
Deep Borehole Disposal of Nuclear Wastes: Opportunities and Challenges 深钻孔处置核废料:机遇与挑战
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.301
F. Schwartz, Yongje Kim, B. Chae
The concept of deep borehole disposal (DBD) for high-level nuclear wastes has been around for about 40 years. Now, the Department of Energy (DOE) in the United States (U.S.) is re-examining this concept through recent studies at Sandia National Laboratory and a field test. With DBD, nuclear waste will be emplaced in boreholes at depths of 3 to 5 km in crystalline basement rocks. Thinking is that these settings will provide nearly intact rock and fluid density stratification, which together should act as a robust geologic barrier, requiring only minimal performance from the engineered components. The Nuclear Waste Technical Review Board (NWTRB) has raised concerns that the deep subsurface is more complicated, leading to science, engineering, and safety issues. However, given time and resources, DBD will evolve substantially in the ability to drill deep holes and make measurements there. A leap forward in technology for drilling could lead to other exciting geological applications. Possible innovations might include deep robotic mining, deep energy production, or crustal sequestration of CO2, and new ideas for nuclear waste disposal. Novel technologies could be explored by Korean geologists through simple proof-of-concept experiments and technology demonstrations.
高放核废料深孔处置(DBD)的概念已经出现了大约40年。现在,美国能源部(DOE)正在通过桑迪亚国家实验室(Sandia National Laboratory)最近的研究和现场测试重新审视这一概念。利用DBD,核废料将被安置在3至5公里深的结晶基底岩石的钻孔中。我们的想法是,这些设置将提供几乎完整的岩石和流体密度分层,它们一起应该充当坚固的地质屏障,只需要最小的工程组件性能。核废料技术审查委员会(NWTRB)已经提出了担忧,认为地下深处更为复杂,会导致科学、工程和安全问题。然而,考虑到时间和资源,DBD在钻深孔并在那里进行测量的能力上将会有很大的发展。钻探技术的飞跃可能会带来其他令人兴奋的地质应用。可能的创新可能包括深层机器人采矿,深层能源生产,或二氧化碳的地壳封存,以及核废料处理的新想法。韩国地质学家可以通过简单的概念验证实验和技术演示来探索新技术。
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引用次数: 4
The Dismantling and Disposal Strategy of a Biological Shield for Minimization of Radioactive Concrete Waste During Decommissioning of a Nuclear Power Plant 核电站退役过程中减少放射性混凝土废物的生物屏蔽拆除与处置策略
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.355
전철승, 김창락
The decommissioning of Kori unit 1, which was permanently shut down in June of 2017, will be the first instance of the dismantling of a commercial nuclear power plant in Korea. The disposal of waste during the dismantling process accounts for a large part of the total decommissioning cost. Therefore, structures consisting of activated and contaminated concrete must be economically and safely dismantled by establishing a proper dismantling strategy. This study focuses on optimized dismantling and disposal scenarios pertaining to a biological shield. Several dismantling cases, regulations and technologies related to waste treatment as these practices pertain to nuclear power plants are analyzed. To minimize the amount of waste from the biological shield dismantling process, an optimized dismantling scenario is presented and disposal alternatives for dismantled concrete waste are proposed.
2017年6月永久关闭的古里核电站1号机组的退役,将是国内第一个商用核电站的退役。拆解过程中的废弃物处理费用占拆解总费用的很大一部分。因此,由活化混凝土和污染混凝土组成的结构必须通过制定适当的拆除策略来经济安全地拆除。本研究的重点是优化拆除和处置方案有关的生物盾牌。分析了几个与核电站有关的拆除案例,以及与废物处理有关的法规和技术。为了最大限度地减少生物屏蔽拆除过程中产生的废物量,提出了一个优化的拆除方案,并提出了拆除混凝土废物的处理方案。
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引用次数: 6
Preliminary Design of the Forced Gas Drying System for Spent Nuclear Fuel Dry Storage 乏燃料干库强制气体干燥系统的初步设计
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.403
Gyung-sun Chae, Kyung-wook Shin, Byeong-mok Park, Jae-hyun Han, Geon-hui Lee, Jae-seok Park
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引用次数: 0
Scaling Up Fabrication of UO2 Porous Pellet With a Simulated Spent Fuel Composition 用模拟乏燃料成分制备UO2多孔球团
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.343
S. Jeon, Jaewon Lee, Joo-Young Yoon, Y. Cho
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引用次数: 5
PRIDE 3D Simulator for Virtual Verification of Remote Handling Procedures in Processing Cell 用于加工单元中远程处理程序虚拟验证的PRIDE三维模拟器
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.333
D. Ryu, Jonghui Han, Sunghyun Kim, Ki-ho Kim, J. K. Lee
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引用次数: 0
Modeling of High-throughput Uranium Electrorefiner and Validation for Different Electrode Configuration 高通量铀电精炼厂建模及不同电极配置的验证
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.321
Young-Min Kim, Dae-young Kim, B. Yoo, Junhyuk Jang, Sung Jai Lee, Sung Bin Park, Hansoo Lee, Jong Hyeon Lee
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引用次数: 0
Preliminary Assessment of Radiological Impact on the Domestic Railroad Transport of High Level Radioactive Waste 高放废物国内铁路运输辐射影响初步评价
Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.381
Myung-Soon Seo, H. Dho, Sung-W. Hong, J. Park
{"title":"Preliminary Assessment of Radiological Impact on the Domestic Railroad Transport of High Level Radioactive Waste","authors":"Myung-Soon Seo, H. Dho, Sung-W. Hong, J. Park","doi":"10.7733/JNFCWT.2017.15.4.381","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.381","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73591591","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions 干贮存条件下乏核燃料混凝土桶屏蔽性能初步分析
Pub Date : 2017-12-15 DOI: 10.7733/jnfcwt.2017.15.4.391
Tae-Man Kim, H. Dho, C. Cho, Jae-Hun Ko
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引用次数: 4
Determination of Radionuclide Concentration Limit for Low and Intermediate-Level Radioactive Waste Disposal Facility II: Application of Optimization Methodology for Underground Silo Type Disposal Facility 中低放废物处置设施放射性核素浓度限值的确定ⅱ:优化方法在地下筒仓式处置设施中的应用
Pub Date : 2017-09-30 DOI: 10.7733/JNFCWT.2017.15.3.257
홍 성욱, 김 민성, 정 강일, 박 진백
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引用次数: 4
期刊
Journal of the Nuclear Fuel Cycle and Waste Technology
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