Pub Date : 2023-01-01DOI: 10.25283/2587-9707-2023-2-113-126
S. Bogatov, V. V. Suskin
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.
{"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}
Pub Date : 2023-01-01DOI: 10.25283/2587-9707-2023-1-77-90
A. Pavliuk, S. Kotlyarevsky, V. S. Zagumennov, R. Kan, V. A. Kuzov, A. V. Mevius
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.
{"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}
Pub Date : 2023-01-01DOI: 10.25283/2587-9707-2023-1-17-22
A. Savkin, E. E. Ostashkina, Yu. T. Slastennikov
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.
{"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}
Pub Date : 2023-01-01DOI: 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}
Pub Date : 2023-01-01DOI: 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}
Pub Date : 2023-01-01DOI: 10.25283/2587-9707-2023-2-41-55
A. Pavliuk, S. Kotlyarevsky, E. Bespala, A. Rif, R. Kan
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.
本文探讨了国外运行的铀-石墨堆(GLEEP, WAGR, BGRR, HTGR)和石墨反射器堆(DIORIT, DR 1)中石墨去除的最佳实践。基于几个案例研究，它考虑了不同的方法，特别是:石墨破碎;水下堆堆井筒淹水拆除及上部生物屏蔽拆除拆卸上部生物屏蔽层，逐层去除石墨块。它讨论了在国际项目下实际执行先进办法的当前趋势、现有挑战和长期计划。
{"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}
Pub Date : 2023-01-01DOI: 10.25283/2587-9707-2023-1-45-57
K. Boldyrev
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.
{"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}
Pub Date : 2023-01-01DOI: 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}
Pub Date : 2023-01-01DOI: 10.25283/2587-9707-2023-2-82-89
A. A. Kalistratov, O. Ilina, A. O. Yudanova, P. V. Semin, Sharbanu Muzdybayeva
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.
{"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}
Pub Date : 2023-01-01DOI: 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}
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