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

筛选
英文 中文
Activation Analysis of Dual-purpose Metal Cask After the End of Design Lifetime for Decommission 双用途金属桶设计寿命退役后的活化分析
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-12-31 DOI: 10.7733/JNFCWT.2016.14.4.343
Tae-Man Kim, Ji Ku, H. Dho, C. Cho, Jae-Hun Ko
{"title":"Activation Analysis of Dual-purpose Metal Cask After the End of Design Lifetime for Decommission","authors":"Tae-Man Kim, Ji Ku, H. Dho, C. Cho, Jae-Hun Ko","doi":"10.7733/JNFCWT.2016.14.4.343","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.4.343","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"43 1","pages":"343-356"},"PeriodicalIF":0.0,"publicationDate":"2016-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77718006","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
The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask 双用途金属桶装载压水堆乏燃料最小冷却周期的评估
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-12-31 DOI: 10.7733/JNFCWT.2016.14.4.411
H. Dho, Tae-Man Kim, C. Cho
{"title":"The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask","authors":"H. Dho, Tae-Man Kim, C. Cho","doi":"10.7733/JNFCWT.2016.14.4.411","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.4.411","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"14 1","pages":"411-422"},"PeriodicalIF":0.0,"publicationDate":"2016-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82797238","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
Aggregate Effects on γ-ray Shielding Characteristic and Compressive Strength of Concrete 集料对混凝土γ射线屏蔽特性和抗压强度的影响
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-12-31 DOI: 10.7733/JNFCWT.2016.14.4.357
Jeong-Hwan Oh, Young-Bum Mun, Jae-Hyung Lee, Hyun-Kook Choi, S. Choi
{"title":"Aggregate Effects on γ-ray Shielding Characteristic and Compressive Strength of Concrete","authors":"Jeong-Hwan Oh, Young-Bum Mun, Jae-Hyung Lee, Hyun-Kook Choi, S. Choi","doi":"10.7733/JNFCWT.2016.14.4.357","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.4.357","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"4 1","pages":"357-365"},"PeriodicalIF":0.0,"publicationDate":"2016-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72824617","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
Comprehensive Development Plans for the Low- and Intermediate-Level Radioactive Waste Disposal Facility in Korea and Preliminary Safety Assessment 韩国中低水平放射性废物处理设施综合发展计划及初步安全性评价
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-12-31 DOI: 10.7733/JNFCWT.2016.14.4.385
K. Jung, Jin Hyeong Kim, Mi-jin Kwon, Mi-seon Jeong, Sung-W. Hong, J. Park
{"title":"Comprehensive Development Plans for the Low- and Intermediate-Level Radioactive Waste Disposal Facility in Korea and Preliminary Safety Assessment","authors":"K. Jung, Jin Hyeong Kim, Mi-jin Kwon, Mi-seon Jeong, Sung-W. Hong, J. Park","doi":"10.7733/JNFCWT.2016.14.4.385","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.4.385","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"6 1","pages":"385-410"},"PeriodicalIF":0.0,"publicationDate":"2016-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88684712","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
Establishment of the Physicochemical and Radiological Database of Raw Materials and By-Products in Domestic Distribution 国内流通原料与副产物理化与放射学数据库的建立
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-12-31 DOI: 10.7733/JNFCWT.2016.14.4.331
Chung-Sup Lim, Jong-Myoung Lim, Ji-young Park, K. Chung, Chang-jong Kim, B. Chang, Young-Yong Ji
{"title":"Establishment of the Physicochemical and Radiological Database of Raw Materials and By-Products in Domestic Distribution","authors":"Chung-Sup Lim, Jong-Myoung Lim, Ji-young Park, K. Chung, Chang-jong Kim, B. Chang, Young-Yong Ji","doi":"10.7733/JNFCWT.2016.14.4.331","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.4.331","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"24 1","pages":"331-341"},"PeriodicalIF":0.0,"publicationDate":"2016-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84224066","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
Study on the Code System for the Off-Site Consequences Assessment of Severe Nuclear Accident 重大核事故场外后果评价代码体系研究
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-12-31 DOI: 10.7733/JNFCWT.2016.14.4.423
Sora Kim, B. Min, Kihyun Park, Byung-Mo Yang, K. Suh
{"title":"Study on the Code System for the Off-Site Consequences Assessment of Severe Nuclear Accident","authors":"Sora Kim, B. Min, Kihyun Park, Byung-Mo Yang, K. Suh","doi":"10.7733/JNFCWT.2016.14.4.423","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.4.423","url":null,"abstract":"인접 국가인 일본의 후쿠시마 원전에서 극한 자연재해로 인한 중대사고가 발생하면서, 국내에서 중대사고 및 확률론적 안전성 평가 (PSA, Probabilistic Safety Assessment)에 대한 중요성이 재인식되었다. 국내에서는 원전의 소외결말을 평가하는 3단계 PSA에 대한 연구개발이 최근까지 거의 이루어지지 않았다. 본 논문에...","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"96 1","pages":"423-434"},"PeriodicalIF":0.0,"publicationDate":"2016-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83937250","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
U.S. Policy and Current Practices for Blending Low-Level Radioactive Waste for Disposal 美国混合处置低放射性废物的政策和现行做法
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-09-30 DOI: 10.7733/jnfcwt.2016.14.3.235
D. Kessel, Chang-Lak Kim
{"title":"U.S. Policy and Current Practices for Blending Low-Level Radioactive Waste for Disposal","authors":"D. Kessel, Chang-Lak Kim","doi":"10.7733/jnfcwt.2016.14.3.235","DOIUrl":"https://doi.org/10.7733/jnfcwt.2016.14.3.235","url":null,"abstract":"In the near future, many countries, including the Republic of Korea, will face a significant increase in low level radioactive waste (LLW) from nuclear power plant decommissioning. The purpose of this paper is to look at blending as a method for enhancing disposal options for low-level radioactive waste from the decommissioning of nuclear reactors. The 2007 U.S. Nuclear Regulatory Commission strategic assessment of the status of the U.S. LLW program identified the need to move to a risk-informed and performance-based regulatory approach for managing LLW. The strategic assessment identified blending waste of varying radionuclide concentrations as a potential means of enhancing options for LLW disposal. The NRC’s position is that concentration averaging or blending can be performed in a way that does not diminish the overall safety of LLW disposal. The revised regulatory requirements for blending LLW are presented in the revised NRC Branch Technical Position for Concentration Averaging and Encapsulation (CA BTP 2015). The changes to the CA BTP that are the most significant for NPP operation, maintenance and decommissioning are reviewed in this paper and a potential application is identified for decommissioning waste in Korea. By far the largest volume of LLW from NPPs will come from decommissioning rather than operation. The large volumes in decommissioning present an opportunity for significant gains in disposal efficiency from blending and concentration averaging. The application of concentration averaging waste from a reactor bio-shield is also presented.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"55 1","pages":"235-243"},"PeriodicalIF":0.0,"publicationDate":"2016-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82839210","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
Study of Classification and Disposal Method for Disused Sealed Radioactive Source in Korea 韩国废弃密封放射源分类与处置方法研究
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-09-30 DOI: 10.7733/jnfcwt.2016.14.3.253
Sukhoon Kim, Juyoul Kim, Seunghee Lee
{"title":"Study of Classification and Disposal Method for Disused Sealed Radioactive Source in Korea","authors":"Sukhoon Kim, Juyoul Kim, Seunghee Lee","doi":"10.7733/jnfcwt.2016.14.3.253","DOIUrl":"https://doi.org/10.7733/jnfcwt.2016.14.3.253","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"46 1","pages":"253-266"},"PeriodicalIF":0.0,"publicationDate":"2016-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88149697","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
Dechlorination/Solidification of LiCl Waste by Using a Synthetic Inorganic Composite with Different Compositions 不同成分合成无机复合材料对LiCl废石的脱氯固化研究
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-09-30 DOI: 10.7733/JNFCWT.2016.14.3.211
Kim Na-young, Choi In-hak, Park Hwan Seo, D. Ahn
{"title":"Dechlorination/Solidification of LiCl Waste by Using a Synthetic Inorganic Composite with Different Compositions","authors":"Kim Na-young, Choi In-hak, Park Hwan Seo, D. Ahn","doi":"10.7733/JNFCWT.2016.14.3.211","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.3.211","url":null,"abstract":"","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"33 1","pages":"211-221"},"PeriodicalIF":0.0,"publicationDate":"2016-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80387995","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: 2
Removal of I by Adsorption with AgX (Ag-impregnated X Zeolite) from High-Radioactive Seawater Waste AgX(浸渍ag的X沸石)吸附去除高放射性海水废物中的ⅰ
Journal of the Nuclear Fuel Cycle and Waste Technology Pub Date : 2016-09-30 DOI: 10.7733/JNFCWT.2016.14.3.223
Eil-Hee Lee, Keunyoung Lee, Kwang-Wook Kim, Hyung‐Ju Kim, I. Kim, D. Chung, J. Moon, Jongwon Choi
{"title":"Removal of I by Adsorption with AgX (Ag-impregnated X Zeolite) from High-Radioactive Seawater Waste","authors":"Eil-Hee Lee, Keunyoung Lee, Kwang-Wook Kim, Hyung‐Ju Kim, I. Kim, D. Chung, J. Moon, Jongwon Choi","doi":"10.7733/JNFCWT.2016.14.3.223","DOIUrl":"https://doi.org/10.7733/JNFCWT.2016.14.3.223","url":null,"abstract":"This study aimed to the adsorption-removal of highradioactive iodide (I) contained in the initially generated high-radioactive seawater waste (HSW), with the use of AgX (Ag-impregnated X zeolite). Adsorption of I by AgX (hereafter denoted as AgX-I adsorption) was increased by increasing the Ag-impregnated concentration in AgX, and its concentration was suitable at about 30 wt%. Because of AgCl precipitation by chloride ions contained in seawater waste, the leaching yields of Ag from AgX (Ag-impregnated concentration : about 30~35 wt%) was less than those in distilled water (< 1 mg/L). AgX-I adsorption was above 99% in the initial iodide concentration (Ci) of 0.01~10 mg/L at m/V (ratio of weight of adsorbent to solution volume)=2.5 g/L. This shows that efficient removal of I is possible. AgX-I adsorption was found to be more effective in distilled water than in seawater waste, and the influence of solution temperature was insignificant. Ag-I adsorption was better described by a Freundlich isotherm rather than a Langmuir isotherm. AgX-I adsorption kinetics can be expressed by a pseudo-second order rate equation. The adsorption rate constants (k2) decreased by increasing Ci, and conversely increased by increasing the ratio of m/V and the solution temperature. This time, the activation energy of AgX-I adsorption was about 6.3 kJ/mol. This suggests that AgX-I adsorption is dominated by physical adsorption with weaker bonds. The evaluation of thermodynamic parameters (a negative Gibbs free energy and a positive Enthalpy) indicates that AgX-I adsorption is a spontaneous reaction (forward reaction), and an endothermic reaction indicating that higher temperatures are favored.","PeriodicalId":17456,"journal":{"name":"Journal of the Nuclear Fuel Cycle and Waste Technology","volume":"72 1","pages":"223-234"},"PeriodicalIF":0.0,"publicationDate":"2016-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84103984","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
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
相关产品
×
本文献相关产品
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信