Pub Date : 2023-10-03DOI: 10.1299/jsmeicone.2023.30.1204
E. Porcheron, Yohan Leblois, T. Gélain, C. Journeau, Romain Berlemont, Antonin Bouland, Gaëtan Bigoin, Rémi Delalez
The general context of the article is to evaluate strategies that can be used to mitigate aerosols dispersion during the fuel debris or corium retrieval of Fukushima damaged reactors. IRSN is involved in several projects led by ONET Technologies along with CEA to provide relevant information to analyze the risk of aerosol resuspension induced by fuel debris retrieval. The knowledge of the aerosol source term emitted during fuel debris retrieval operations is one of the key issues for the assessment of aerosol dispersion that can lead to the release of radionuclides into the environment. Such information are also necessary to define an efficient strategy to mitigate this risk. Various mitigation means could be implemented during the decommissioning of Fukushima Daiichi damaged reactors, depending on the operations such as cutting of fuel debris or metallic structures or investigation in Primary Containment Vessel (PCV) by robots. It is also important to consider accidental scenarios such as earthquake event, to define countermeasures limiting the consequence in terms of safety and radioprotection. We propose to study various mitigation means such as the spray scrubbing technology used to collect airborne particles and therefore limit their dispersion during the cutting operations. Resuspension of deposited particles may also occur during the decommissioning operations due to various type of stress, such as aeraulic, mechanical, vibrational and also during underwater operations. To address these particle resuspension issues, another mitigation means made by coating of resins is introduced.
{"title":"AEROSOL MITIGATION MEANS FOR FUKUSHIMA DAIICHI FUEL DEBRIS REMOVAL","authors":"E. Porcheron, Yohan Leblois, T. Gélain, C. Journeau, Romain Berlemont, Antonin Bouland, Gaëtan Bigoin, Rémi Delalez","doi":"10.1299/jsmeicone.2023.30.1204","DOIUrl":"https://doi.org/10.1299/jsmeicone.2023.30.1204","url":null,"abstract":"The general context of the article is to evaluate strategies that can be used to mitigate aerosols dispersion during the fuel debris or corium retrieval of Fukushima damaged reactors. IRSN is involved in several projects led by ONET Technologies along with CEA to provide relevant information to analyze the risk of aerosol resuspension induced by fuel debris retrieval. The knowledge of the aerosol source term emitted during fuel debris retrieval operations is one of the key issues for the assessment of aerosol dispersion that can lead to the release of radionuclides into the environment. Such information are also necessary to define an efficient strategy to mitigate this risk. Various mitigation means could be implemented during the decommissioning of Fukushima Daiichi damaged reactors, depending on the operations such as cutting of fuel debris or metallic structures or investigation in Primary Containment Vessel (PCV) by robots. It is also important to consider accidental scenarios such as earthquake event, to define countermeasures limiting the consequence in terms of safety and radioprotection. We propose to study various mitigation means such as the spray scrubbing technology used to collect airborne particles and therefore limit their dispersion during the cutting operations. Resuspension of deposited particles may also occur during the decommissioning operations due to various type of stress, such as aeraulic, mechanical, vibrational and also during underwater operations. To address these particle resuspension issues, another mitigation means made by coating of resins is introduced.","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"8 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-10-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139323864","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 : 2021-10-19DOI: 10.1299/jsmeicone.2019.27.1025
H. Yamano, A. Vasile, S. Kang, Tyler Summer, H. Tsige-Tamirat, Jin Wang, I. Ashurko
{"title":"ACTIVITIES OF THE GIF SAFETY AND OPERATION PROJECT OF SODIUM-COOLED FAST REACTOR SYSTEMS","authors":"H. Yamano, A. Vasile, S. Kang, Tyler Summer, H. Tsige-Tamirat, Jin Wang, I. Ashurko","doi":"10.1299/jsmeicone.2019.27.1025","DOIUrl":"https://doi.org/10.1299/jsmeicone.2019.27.1025","url":null,"abstract":"","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"120 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-10-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128251436","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 : 2019-06-27DOI: 10.1299/JSMEICONE.2019.27.1827
D. Invernizzi, Akira Asahara, G. Locatelli, S. Yanagihara
{"title":"REGULATORY CHALLENGES OF NUCLEAR DECOMMISSIONING PROJECTS AND PROGRAMMES FROM THE VIEWPOINT OF PROJECT MANAGEMENT","authors":"D. Invernizzi, Akira Asahara, G. Locatelli, S. Yanagihara","doi":"10.1299/JSMEICONE.2019.27.1827","DOIUrl":"https://doi.org/10.1299/JSMEICONE.2019.27.1827","url":null,"abstract":"","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"49 7-8","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132811356","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 : 2019-06-27DOI: 10.1299/JSMEICONE.2019.27.1235
Benito Mignacca, Ahmad Hasan Alawneh, G. Locatelli
One of the key characteristics of small modular reactors (SMRs), as their name emphasised, is the modularization. Modularization implies factory production, which in turn implies transportation of large, heavy, complex and fragile modules from the factory to the site. Various vendors and organisations are developing several SMR concepts and designs, but there are extremely limited information about the crucial element of modules transportation. Conversely, in other industries (e.g. Oil & Gas), the experience on modules transportation is much greater. This paper provides a structured analysis for the knowledge transfer from the general literature (i.e. other major infrastructure) to the SMR world. Firstly, the paper provides a summary of the literature about transporting large modules. In the second part, the paper presents and discusses the results of a series of interviews with transport industry experts about large modules transportation. The third part provides a summary of the findings and the key takeaways.
{"title":"TRANSPORTATION OF SMALL MODULAR REACTOR MODULES: WHAT DO THE EXPERTS SAY?","authors":"Benito Mignacca, Ahmad Hasan Alawneh, G. Locatelli","doi":"10.1299/JSMEICONE.2019.27.1235","DOIUrl":"https://doi.org/10.1299/JSMEICONE.2019.27.1235","url":null,"abstract":"One of the key characteristics of small modular reactors (SMRs), as their name emphasised, is the modularization. Modularization implies factory production, which in turn implies transportation of large, heavy, complex and fragile modules from the factory to the site. Various vendors and organisations are developing several SMR concepts and designs, but there are extremely limited information about the crucial element of modules transportation. Conversely, in other industries (e.g. Oil & Gas), the experience on modules transportation is much greater. This paper provides a structured analysis for the knowledge transfer from the general literature (i.e. other major infrastructure) to the SMR world. Firstly, the paper provides a summary of the literature about transporting large modules. In the second part, the paper presents and discusses the results of a series of interviews with transport industry experts about large modules transportation. The third part provides a summary of the findings and the key takeaways.","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"45 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"134539885","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 : 2019-05-31DOI: 10.1299/jsmeicone.2019.27.2082
E. Osigwe, A. Gad-Briggs, P. Pilidis, T. Nikolaidis, S. Sampath
The cycle configuration of the energy conversion system in a nuclear power plant tends to have a governing effect on the overall performance and acquisition cost. Interestingly, one factor that could greatly affect the design choice of the cycle configuration which may not have been explored extensively in many literatures reviewed is the choice of the working fluid. This paper presents a technical analysis on the effect of working fluid on selection of the cycle arrangement for a Generation IV nuclear power plant. It provides insight on potential performance gains that justifies the benefit for an additional cost of a complex cycle, and how the working fluid can influence this choice. The study identifies candidate working fluid that may be suitable for simple, inter-cooled-recuperated, recuperated and other complex cycles. The results obtained shows that for fluid like carbon dioxide, its optimal performance is achieved above it critical points which will require pressurizing the system or operating at high pressure ratio, hence, it would be suitable for a re-compressed inter-cooled cycle configuration. Similar, for fluid like helium with low molecular weight and high gas properties, the simple cycle configuration seem more realistic for its highest cycle efficiency of 41% and turbomachinery design.
{"title":"EFFECT OF WORKING FLUID ON SELECTION OF GAS TURBINE CYCLE CONFIGURATION FOR GEN-IV NUCLEAR POWER PLANT SYSTEM","authors":"E. Osigwe, A. Gad-Briggs, P. Pilidis, T. Nikolaidis, S. Sampath","doi":"10.1299/jsmeicone.2019.27.2082","DOIUrl":"https://doi.org/10.1299/jsmeicone.2019.27.2082","url":null,"abstract":"The cycle configuration of the energy conversion system in a nuclear power plant tends to have a governing effect on the overall performance and acquisition cost. Interestingly, one factor that could greatly affect the design choice of the cycle configuration which may not have been explored extensively in many literatures reviewed is the choice of the working fluid. This paper presents a technical analysis on the effect of working fluid on selection of the cycle arrangement for a Generation IV nuclear power plant. It provides insight on potential performance gains that justifies the benefit for an additional cost of a complex cycle, and how the working fluid can influence this choice. The study identifies candidate working fluid that may be suitable for simple, inter-cooled-recuperated, recuperated and other complex cycles. The results obtained shows that for fluid like carbon dioxide, its optimal performance is achieved above it critical points which will require pressurizing the system or operating at high pressure ratio, hence, it would be suitable for a re-compressed inter-cooled cycle configuration. Similar, for fluid like helium with low molecular weight and high gas properties, the simple cycle configuration seem more realistic for its highest cycle efficiency of 41% and turbomachinery design.","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"675 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132418409","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 : 2019-05-24DOI: 10.1299/jsmeicone.2019.27.2085
E. Osigwe, A. Gad-Briggs, P. Pilidis, T. Nikolaidis, S. Sampath
The Inventory Control System (ICS) offer unique characteristics when modulating the gas turbine output power to match the required load demand. The unique opportunities it offers have made it to be widely used in most nuclear powered closed-cycle gas turbine plant design and operations. This paper presents a technical study on how the different working fluid options affect the design and performance characteristics of the inventory control system. The results from this study shows that using helium as cycle working fluid offers an advantage in terms of Reynolds effect on cycle efficiency and also enable the design for compact inventory tank size and weight which could have a direct effect on the capital cost, due to its thermodynamic characteristics. However, the long term operational cost of helium compared with other working fluid utilized in this study provides a reasonable argument to justify any investment decision.
{"title":"INVENTORY CONTROL SYSTEMS FOR NUCLEAR POWERED CLOSED-CYCLE GAS TURBINE: TECHNICAL STUDIES ON EFFECT OF WORKING FLUID OPTIONS","authors":"E. Osigwe, A. Gad-Briggs, P. Pilidis, T. Nikolaidis, S. Sampath","doi":"10.1299/jsmeicone.2019.27.2085","DOIUrl":"https://doi.org/10.1299/jsmeicone.2019.27.2085","url":null,"abstract":"The Inventory Control System (ICS) offer unique characteristics when modulating the gas turbine output power to match the required load demand. The unique opportunities it offers have made it to be widely used in most nuclear powered closed-cycle gas turbine plant design and operations. This paper presents a technical study on how the different working fluid options affect the design and performance characteristics of the inventory control system. The results from this study shows that using helium as cycle working fluid offers an advantage in terms of Reynolds effect on cycle efficiency and also enable the design for compact inventory tank size and weight which could have a direct effect on the capital cost, due to its thermodynamic characteristics. However, the long term operational cost of helium compared with other working fluid utilized in this study provides a reasonable argument to justify any investment decision.","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"56 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122048737","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}
{"title":"STUDY ON SURFACE PORE CHARACTERISTIC AND HYDROPHILICITY OF CARBON MATERIALS IN HTGR","authors":"Shengchao Ma, Kaiyue Shen, Huaqiang Yin, Xuedong He, Jun Li, Yingchao Meng","doi":"10.1299/jsmeicone.2019.27.1063","DOIUrl":"https://doi.org/10.1299/jsmeicone.2019.27.1063","url":null,"abstract":"","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"5 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129389176","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 : 2019-05-18DOI: 10.1299/jsmeicone.2019.27.2105
Y. Cho, H. Son, J. Han, S. J. Kim, B. Park, H. Shin, Hwansoo Lee
{"title":"APPLICATION OF TIME-DEPENDENT GROWING MESH FOR CRUD GROWTH SIMULATION IN SINGLE ROD SCALE","authors":"Y. Cho, H. Son, J. Han, S. J. Kim, B. Park, H. Shin, Hwansoo Lee","doi":"10.1299/jsmeicone.2019.27.2105","DOIUrl":"https://doi.org/10.1299/jsmeicone.2019.27.2105","url":null,"abstract":"","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"11 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128457376","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 : 2019-05-18DOI: 10.1299/jsmeicone.2019.27.1152
Yun Wang, Hideo Watanabe, Dongyue Chen, J. Kaneda, N. Shigenaka
{"title":"EFFECT OF TA ADDITION ON IRRADIATION RESISTANCE PROPERTIES OF AUSTENITIC STAINLESS STEELS FOR REACTOR PRESSURE VESSEL INTERNALS","authors":"Yun Wang, Hideo Watanabe, Dongyue Chen, J. Kaneda, N. Shigenaka","doi":"10.1299/jsmeicone.2019.27.1152","DOIUrl":"https://doi.org/10.1299/jsmeicone.2019.27.1152","url":null,"abstract":"","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"216 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"134223138","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 : 2019-05-18DOI: 10.1299/JSMEICONE.2019.27.1840
Ayumi Takashima, A. Gofuku
{"title":"AN INVESTIGATION OF FUNCTIONAL MODEL AND TEXT PRESENTATION FOR EXPLANATION DISPLAY OF COUNTER OPERATION PROCEDURE IN AN EMERGENCY SITUATION OF PLANTS","authors":"Ayumi Takashima, A. Gofuku","doi":"10.1299/JSMEICONE.2019.27.1840","DOIUrl":"https://doi.org/10.1299/JSMEICONE.2019.27.1840","url":null,"abstract":"","PeriodicalId":116763,"journal":{"name":"The Proceedings of the International Conference on Nuclear Engineering (ICONE)","volume":"71 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122795594","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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