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Journal of Hazardous, Toxic, and Radioactive Waste最新文献

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Accounting for engineered barrier saturation, steel container corrosion, hydrogen production and transfer within fractured rock in the assessments of low sorbing radionuclides release from geological disposal facilities 在地质处置设施低吸收性放射性核素释放评估中，考虑工程屏障饱和、钢容器腐蚀、断裂岩石内氢气的产生和转移
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.25283/2587-9707-2023-2-113-126
S. Bogatov, V. V. Suskin
{"title":"Accounting for engineered barrier saturation, steel container corrosion, hydrogen production and transfer within fractured rock in the assessments of low sorbing radionuclides release from geological disposal facilities","authors":"S. Bogatov, V. V. Suskin","doi":"10.25283/2587-9707-2023-2-113-126","DOIUrl":"https://doi.org/10.25283/2587-9707-2023-2-113-126","url":null,"abstract":"The paper discusses the influence of bentonite saturation, package failure and water conductive fracture network on the transport of long-lived low sorbing radionuclides in geological disposal facilities (DGR). Based on the example of 129I, the study evaluates the influence of space and time dispersion of radionuclide transport and processes mentioned above on the long-term DGR safety. It demonstrates that these effects can cause significant radionuclide retention, nevertheless having minor impact on the long-term DGR safety as regards low sorbing nuclides with their half-lives amounting to over hundreds of thousand years. The paper also considers the opportunities for enhancing the GDF safety considering such radionuclides.","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"1 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82954122","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
Methodological approaches to the survey of storage facilities for the radioactive waste from uranium-graphite reactors 铀-石墨反应堆放射性废料贮存设施调查的方法学方法
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.25283/2587-9707-2023-1-77-90
A. Pavliuk, S. Kotlyarevsky, V. S. Zagumennov, R. Kan, V. A. Kuzov, A. V. Mevius
{"title":"Methodological approaches to the survey of storage facilities for the radioactive waste from uranium-graphite reactors","authors":"A. Pavliuk, S. Kotlyarevsky, V. S. Zagumennov, R. Kan, V. A. Kuzov, A. V. Mevius","doi":"10.25283/2587-9707-2023-1-77-90","DOIUrl":"https://doi.org/10.25283/2587-9707-2023-1-77-90","url":null,"abstract":"The article presents methods and a general survey procedure for storage facilities with radioactive waste generated during the operation of uranium-graphite reactors. It presents the experience from the application of different survey methods and relevant findings. The paper describes the key areas for further improvement of the survey methods, including the results from the mock-up tests based on various methods applied for arranging penetrations in the radioactive waste volume providing access to the bottom waste layers. The approaches presented in the article can be adapted to explore other storage facility types arranged during nuclear decommissioning.","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"19 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84747653","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
Development of a Cement Compound Formulation for the Solidification of Evaporation Residues from a New Generation Nuclear Power Plant with a VVER‑1200 Reactor Unit 新一代VVER - 1200反应堆机组核电站蒸发残留物固化用水泥复合配方的研制
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.25283/2587-9707-2023-1-17-22
A. Savkin, E. E. Ostashkina, Yu. T. Slastennikov
{"title":"Development of a Cement Compound Formulation for the Solidification of Evaporation Residues from a New Generation Nuclear Power Plant with a VVER‑1200 Reactor Unit","authors":"A. Savkin, E. E. Ostashkina, Yu. T. Slastennikov","doi":"10.25283/2587-9707-2023-1-17-22","DOIUrl":"https://doi.org/10.25283/2587-9707-2023-1-17-22","url":null,"abstract":"The paper presents a formulation developed to produce cement compound based on a mockup evaporation residue and a genuine evaporation residue from the Novovoronezh NPP with a VVER-type reactor unit given a salt content of 25 to 33 wt.%. The study experimentally confirms that the quality indicators of the resulting compound comply with NP-019-15 requirements.","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"42 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78781310","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
Oxidative and Photochemical Processes for Soft Drink–Industry Wastewater Treatment 软饮料工业废水的氧化和光化学处理
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.1061/jhtrbp.hzeng-1206
Anil Swain, N. Remya
{"title":"Oxidative and Photochemical Processes for Soft Drink–Industry Wastewater Treatment","authors":"Anil Swain, N. Remya","doi":"10.1061/jhtrbp.hzeng-1206","DOIUrl":"https://doi.org/10.1061/jhtrbp.hzeng-1206","url":null,"abstract":"","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"37 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90933900","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
A Review of Mercury Waste Management in the ASEAN Oil and Gas Industry 东盟石油和天然气工业汞废物管理综述
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.1061/(asce)hz.2153-5515.0000737
H. Le, W. Punurai, N. Zawawi, O. Yaakob, Nhung Thi Phuong Nguyen, Thanh Thanh Le, Kiet Van Nguyen, Sari Amelia, Nurul Anis Kamarudin, H. Kang, Sy Van Le
{"title":"A Review of Mercury Waste Management in the ASEAN Oil and Gas Industry","authors":"H. Le, W. Punurai, N. Zawawi, O. Yaakob, Nhung Thi Phuong Nguyen, Thanh Thanh Le, Kiet Van Nguyen, Sari Amelia, Nurul Anis Kamarudin, H. Kang, Sy Van Le","doi":"10.1061/(asce)hz.2153-5515.0000737","DOIUrl":"https://doi.org/10.1061/(asce)hz.2153-5515.0000737","url":null,"abstract":"","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"49 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75329355","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
Graphite Removal from Uranium-Graphite Reactors: International Experience and Approaches 铀-石墨反应器中石墨的去除:国际经验和方法
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.25283/2587-9707-2023-2-41-55
A. Pavliuk, S. Kotlyarevsky, E. Bespala, A. Rif, R. Kan
{"title":"Graphite Removal from Uranium-Graphite Reactors: International Experience and Approaches","authors":"A. Pavliuk, S. Kotlyarevsky, E. Bespala, A. Rif, R. Kan","doi":"10.25283/2587-9707-2023-2-41-55","DOIUrl":"https://doi.org/10.25283/2587-9707-2023-2-41-55","url":null,"abstract":"The article explores the best practices for graphite removal from the stacks of uranium-graphite reactors (GLEEP, WAGR, BGRR, HTGR) and reactors with graphite reflectors (DIORIT, DR 1) operated abroad. Based on several case studies, it considers different approaches, in particular: graphite crushing; underwater stack demolition by reactor shaft flooding and upper biological shield dismantling; dismantlement of the upper biological shield and layer-bylayer graphite block removal. It discusses current trends, existing challenges and long-term plans for the practical implementation of advanced approaches under international projects.","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"6 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88605923","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
Modelling carbon steel corrosion considering different factors seeking to forecast the container lifetime 考虑不同因素的碳钢腐蚀模型，寻求预测容器寿命
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.25283/2587-9707-2023-1-45-57
K. Boldyrev
{"title":"Modelling carbon steel corrosion considering different factors seeking to forecast the container lifetime","authors":"K. Boldyrev","doi":"10.25283/2587-9707-2023-1-45-57","DOIUrl":"https://doi.org/10.25283/2587-9707-2023-1-45-57","url":null,"abstract":"The paper overviews the studies dealing with carbon steel corrosion under underground disposal conditions. It presents a model of carbon steel corrosion considering the impact produced by bentonite taking into account oxidation kinetics, steel surface inhibition due to its blocking by corrosion products, as well as cation sorption on the bentonite material. Under the study, the model verification was carried out based on a comparation with the literature data. The simulation showed close agreement of the calculated corrosion rates with the experimental results. The findings of the study may be used to forecast the corrosion of engineered carbon steel safety barriers.","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"55 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80440642","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
Performance and Economic Evaluation of Resin Wafer Electro-Deionization for Cooling Water Blowdown Desalination 冷却水排污海水淡化用树脂薄片电去离子的性能及经济评价
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.1061/jhtrbp.hzeng-1196
Po-Chih Tseng, Tse-Lun Chen, P. Chiang
{"title":"Performance and Economic Evaluation of Resin Wafer Electro-Deionization for Cooling Water Blowdown Desalination","authors":"Po-Chih Tseng, Tse-Lun Chen, P. Chiang","doi":"10.1061/jhtrbp.hzeng-1196","DOIUrl":"https://doi.org/10.1061/jhtrbp.hzeng-1196","url":null,"abstract":"","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"23 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82113698","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
Waterproofing properties of clay-based barrier materials and their experimental demonstration 粘土基阻隔材料的防水性能及其实验验证
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.25283/2587-9707-2023-2-82-89
A. A. Kalistratov, O. Ilina, A. O. Yudanova, P. V. Semin, Sharbanu Muzdybayeva
{"title":"Waterproofing properties of clay-based barrier materials and their experimental demonstration","authors":"A. A. Kalistratov, O. Ilina, A. O. Yudanova, P. V. Semin, Sharbanu Muzdybayeva","doi":"10.25283/2587-9707-2023-2-82-89","DOIUrl":"https://doi.org/10.25283/2587-9707-2023-2-82-89","url":null,"abstract":"The article presents research data visually demonstrating the behavior of barrier clay materials with different mineral compositions when interacting with water. It shows that bentonite clays have higher waterproofing capacity: increased portion of kaolin in the mixture (decreased portion of montmorillonite) yields in a decreased waterproofing capacity of clay materials. It can be concluded that the addition of kaolinite to bentonite has negative effect on the waterproofing capacity of clay materials used in the engineered safety barriers construction.","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"152 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74857888","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
Flow and Transport Analysis and Suggested Optimal CAB Design Charts under Varying Hydraulic Conditions 不同水力条件下的流量与输运分析及CAB优化设计方案建议
IF 2.7
Journal of Hazardous, Toxic, and Radioactive Waste Pub Date : 2023-01-01 DOI: 10.1061/(asce)hz.2153-5515.0000730
Pratiksha Pandey, S. Mathur, V. Sivakumar
{"title":"Flow and Transport Analysis and Suggested Optimal CAB Design Charts under Varying Hydraulic Conditions","authors":"Pratiksha Pandey, S. Mathur, V. Sivakumar","doi":"10.1061/(asce)hz.2153-5515.0000730","DOIUrl":"https://doi.org/10.1061/(asce)hz.2153-5515.0000730","url":null,"abstract":"","PeriodicalId":15963,"journal":{"name":"Journal of Hazardous, Toxic, and Radioactive Waste","volume":"86 1","pages":""},"PeriodicalIF":2.7,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81315228","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
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