Pub Date : 2017-12-15DOI: 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}
Pub Date : 2017-12-15DOI: 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。
{"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}
Pub Date : 2017-12-15DOI: 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.
{"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}
Pub Date : 2017-12-15DOI: 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}
Pub Date : 2017-12-15DOI: 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}
Pub Date : 2017-12-15DOI: 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}
Pub Date : 2017-12-15DOI: 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}
Pub Date : 2017-12-15DOI: 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}
Pub Date : 2017-12-15DOI: 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}
Pub Date : 2017-09-30DOI: 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}
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