Journal of Nuclear Fuel Cycle and Waste Technology最新文献_第4页

Evaluation of Exposure Dose and Working Hours for Near Surface Disposal Facility 近地表处置设施的照射剂量和工作时间评价

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-12-30 DOI: 10.7733/jnfcwt.2022.039

Yeseul Cho, H. Dho, H. Kang, C. Cho

引用次数: 1

International Joint Research for the Colloid Formation and Migration in Grimsel Test Site: Current Status and Perspectives Grimsel试验场胶体形成与运移的国际联合研究:现状与展望

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-12-30 DOI: 10.7733/jnfcwt.2022.034

S. Lee, Jin-Seok Kim, Bong-Ju Kim, Jae-Kwang Lee, Seung Yeop Lee, Jang-Soon Kwon

引用次数: 0

Radiochemical Analysis of Filters Used During the Decommissioning of Research Reactors for Disposal 研究堆退役处置用过滤器的放射化学分析

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-12-30 DOI: 10.7733/jnfcwt.2022.035

Kyungwon Suh, Jung Bo Yoo, K. Choi, Gi-Yong Kim, Si-duk Oh, Kanghyun Yoo, Kwang Eun Lee, S. Lee, Young Sang Lee, Hyeju Lee, Junhyuck Kim, K. Jung, Sora Choi, T. Park

引用次数: 1

Repurposing a Spent Nuclear Fuel Cask for Disposal of Solid Intermediate Level Radioactive Waste From Decommissioning of a Nuclear Power Plantin Korea 利用乏燃料桶处理韩国核电厂退役中放射性固体废物的研究

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-09-30 DOI: 10.7733/jnfcwt.2022.024

Wonjune Mah, Chang-Lak Kim

引用次数: 0

Safety Analysis of Concrete Treatment Workers in Decommissioning of Nuclear Power Plant 核电厂退役混凝土处理工人的安全分析

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-09-30 DOI: 10.7733/jnfcwt.2022.027

Young Hwan Hwang, S. Kim, Mi-hyun Lee, S. Hong, Cheon-Woo Kim

{"title":"Safety Analysis of Concrete Treatment Workers in Decommissioning of Nuclear Power Plant","authors":"Young Hwan Hwang, S. Kim, Mi-hyun Lee, S. Hong, Cheon-Woo Kim","doi":"10.7733/jnfcwt.2022.027","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.027","url":null,"abstract":"Nuclear power plant decommissioning generates significant concrete waste, which is slightly contaminated, and expected to be classified as clearance concrete waste. Clearance concrete waste is generally crushed into rubble at the site or a satellite treatment facility for practical disposal purposes. During the process, workers are exposed to radiation from the nuclides in concrete waste. The treatment processes consist of concrete cutting/crushing, transportation, and loading/unloading. Work - ers’ radiation exposure during the process was systematically studied. A shielding package comprising a cylindrical and hexahedron structure was considered to reduce workers’ radiation exposure, and improved the treatment process’s efficiency. The shielding package’s effect on workers’ radiation exposure during the cutting and crushing process was also studied. The calculated annual radiation exposure of concrete treatment workers was below 1 mSv, which is the annual radiation exposure limit for members of the public. It was also found that workers involved in cutting and crushing were exposed the most.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"47 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82217798","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

Water Sorption/Desorption Characteristics of Eutectic LiCl-KCl Salt-Occluded Zeolites 共晶LiCl-KCl盐封沸石的吸水/解吸特性

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-09-30 DOI: 10.7733/jnfcwt.2022.021

Allison Harward, Levi D. Gardner, Claire M. Decker Oldham, Krista Carlson, T. Yoo, G. Fredrickson, Michael N. Patterson, M. Simpson

引用次数: 1

Damage Monitoring of Concrete With Acoustic Emission Method for Nuclear Waste Storage: Effect of Temperature and Water Immersion 核废料贮存混凝土声发射损伤监测:温度和浸水的影响

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-09-30 DOI: 10.7733/jnfcwt.2022.030

Juneho Park, T. Kwon, Gyeol Han, Jin-Seop Kim, Chang-Ho Hong, Hang-Lo Lee

引用次数: 0

The Transport of Radionuclides Released From Nuclear Facilities and Nuclear Wastes in the Marine Environment at Oceanic Scales 海洋尺度下核设施和核废料释放的放射性核素在海洋环境中的转运

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-09-30 DOI: 10.7733/jnfcwt.2022.029

R. Periáñez

引用次数: 0

Experimental Evaluation of the Thermal Integrity of a Large Capacity Pressurized Heavy Water Reactor Transport Cask 大容量重水堆输送桶热完整性实验评价

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-09-30 DOI: 10.7733/jnfcwt.2022.028

K. Bang, Yun-young Yang, W. Choi

{"title":"Experimental Evaluation of the Thermal Integrity of a Large Capacity Pressurized Heavy Water Reactor Transport Cask","authors":"K. Bang, Yun-young Yang, W. Choi","doi":"10.7733/jnfcwt.2022.028","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.028","url":null,"abstract":"The safety of a KTC-360 transport cask, a large-capacity pressurized heavy-water reactor transport cask that transports CANDU spent nuclear fuel discharged from the reactor after burning in a pressurized heavy-water reactor, must be demon-strated under the normal transport and accident conditions specified under transport cask regulations. To confirm the thermal integrity of this cask under normal transport and accident conditions, high-temperature and fire tests were performed using a one-third slice model of an actual KTC-360 cask. The results revealed that the surface temperature of the cask was 62°C, indicating that such casks must be transported separately. The highest temperature of the CANDU spent nuclear fuel was pre - dicted to be lower than the melting temperature of Zircaloy-4, which was the sheath material used. Therefore, if normal op - erating conditions are applied, the thermal integrity of a KTC-360 cask can be maintained under normal transport conditions. The fire test revealed that the maximum temperatures of the structural materials, stainless steel, and carbon steel were 446°C lower than the permitted maximum temperatures, proving the thermal integrity of the cask under fire accident conditions.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"1 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79187321","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

Bioremediation Options for Nuclear Sites a Review of an Emerging Technology 核设施生物修复方案:一项新兴技术综述

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Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-09-30 DOI: 10.7733/jnfcwt.2022.026

Callum Robinson, White Matthew, S. Shaw, K. Morris, J. Graham, J. Lloyd

{"title":"Bioremediation Options for Nuclear Sites a Review of an Emerging Technology","authors":"Callum Robinson, White Matthew, S. Shaw, K. Morris, J. Graham, J. Lloyd","doi":"10.7733/jnfcwt.2022.026","DOIUrl":"https://doi.org/10.7733/jnfcwt.2022.026","url":null,"abstract":"60+ Years of nuclear power generation has led to a significant legacy of radioactively contaminated land at a number of nuclear licenced “mega sites” around the world. The safe management and remediation of these sites is key to ensuring there environmental stewardship in the long term. Bioremediation utilizes a variety of microbially mediated processes such as, enzymatically driven metal reduction or biominerialisation, to sequester radioactive contaminants from the subsurface limiting their migration through the geosphere. Additionally, some of these process can provide environmentally stable sinks for radioactive contaminants, through formation of highly insoluble mineral phases such as calcium phosphates and carbonates, which can incorporate a range of radionuclides into their structure. Bioremediation options have been consid - ered and deployed in preference to conventional remediation techniques at a number of nuclear “mega” sites. Here, we review the applications of bioremediation technologies at three key nuclear licenced sites; Rifle and Hanford, USA and Sellafield, UK, in the remediation of radioactively contaminated land.","PeriodicalId":36762,"journal":{"name":"Journal of Nuclear Fuel Cycle and Waste Technology","volume":"17 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2022-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73041893","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