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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
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.313
A. Lee, B. Park
{"title":"A Study on Electrochemical Behaviors of Samarium Ions in the Molten LiCl-KCl Eutectic Using Optically Transparent Electrode","authors":"A. Lee, B. Park","doi":"10.7733/JNFCWT.2017.15.4.313","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.313","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"26 1","pages":"313-320"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86678457","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
Deep Borehole Disposal of Nuclear Wastes: Opportunities and Challenges 深钻孔处置核废料:机遇与挑战
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.301
F. Schwartz, Yongje Kim, B. Chae
{"title":"Deep Borehole Disposal of Nuclear Wastes: Opportunities and Challenges","authors":"F. Schwartz, Yongje Kim, B. Chae","doi":"10.7733/JNFCWT.2017.15.4.301","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.301","url":null,"abstract":"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.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"210 1","pages":"301-312"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77004488","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: 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
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.355
전철승, 김창락
{"title":"The Dismantling and Disposal Strategy of a Biological Shield for Minimization of Radioactive Concrete Waste During Decommissioning of a Nuclear Power Plant","authors":"전철승, 김창락","doi":"10.7733/JNFCWT.2017.15.4.355","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.355","url":null,"abstract":"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.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"2011 1","pages":"355-367"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86351828","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: 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
Journal of the Nuclear Fuel Cycle and Waste Technology 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
{"title":"Preliminary Design of the Forced Gas Drying System for Spent Nuclear Fuel Dry Storage","authors":"Gyung-sun Chae, Kyung-wook Shin, Byeong-mok Park, Jae-hyun Han, Geon-hui Lee, Jae-seok Park","doi":"10.7733/JNFCWT.2017.15.4.403","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.403","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":"403-409"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80866429","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: 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
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2017-12-15 DOI: 10.7733/JNFCWT.2017.15.4.343
S. Jeon, Jaewon Lee, Joo-Young Yoon, Y. Cho
{"title":"Scaling Up Fabrication of UO2 Porous Pellet With a Simulated Spent Fuel Composition","authors":"S. Jeon, Jaewon Lee, Joo-Young Yoon, Y. Cho","doi":"10.7733/JNFCWT.2017.15.4.343","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.343","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"94 1","pages":"343-353"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91024142","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: 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
Journal of the Nuclear Fuel Cycle and Waste Technology 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
{"title":"PRIDE 3D Simulator for Virtual Verification of Remote Handling Procedures in Processing Cell","authors":"D. Ryu, Jonghui Han, Sunghyun Kim, Ki-ho Kim, J. K. Lee","doi":"10.7733/JNFCWT.2017.15.4.333","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.333","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":"333-341"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85816573","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: 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
Journal of the Nuclear Fuel Cycle and Waste Technology 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
{"title":"Modeling of High-throughput Uranium Electrorefiner and Validation for Different Electrode Configuration","authors":"Young-Min Kim, Dae-young Kim, B. Yoo, Junhyuk Jang, Sung Jai Lee, Sung Bin Park, Hansoo Lee, Jong Hyeon Lee","doi":"10.7733/JNFCWT.2017.15.4.321","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.4.321","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"74 1","pages":"321-332"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77813909","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: 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
Journal of the Nuclear Fuel Cycle and Waste Technology 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":"57 1","pages":"381-390"},"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
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2017-12-15 DOI: 10.7733/jnfcwt.2017.15.4.391
Tae-Man Kim, H. Dho, C. Cho, Jae-Hun Ko
{"title":"Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions","authors":"Tae-Man Kim, H. Dho, C. Cho, Jae-Hun Ko","doi":"10.7733/jnfcwt.2017.15.4.391","DOIUrl":"https://doi.org/10.7733/jnfcwt.2017.15.4.391","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"65 1","pages":"391-402"},"PeriodicalIF":0.0,"publicationDate":"2017-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85398969","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: 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
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2017-09-30 DOI: 10.7733/JNFCWT.2017.15.3.257
홍 성욱, 김 민성, 정 강일, 박 진백
{"title":"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","authors":"홍 성욱, 김 민성, 정 강일, 박 진백","doi":"10.7733/JNFCWT.2017.15.3.257","DOIUrl":"https://doi.org/10.7733/JNFCWT.2017.15.3.257","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":"257-264"},"PeriodicalIF":0.0,"publicationDate":"2017-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83554437","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: 4
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