Design and Analysis of Nuclear Transportation Cask Using Phase Changing Material
In the nuclear sector, secure transportation of radioactive materials is crucial in the nuclear sector, and cask design and analysis are crucial for maintaining fuel integrity. Peak cladding temperature (PCT) is a significant factor in fuel failure likelihood. This research provides a thorough appro...
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| Language: | English |
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University North
2025-01-01
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| Series: | Tehnički Glasnik |
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| Online Access: | https://hrcak.srce.hr/file/473487 |
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| author | Girish Venkatesh Gudi R. G. Nagraj Abhijit Dandavate |
| author_facet | Girish Venkatesh Gudi R. G. Nagraj Abhijit Dandavate |
| author_sort | Girish Venkatesh Gudi |
| collection | DOAJ |
| description | In the nuclear sector, secure transportation of radioactive materials is crucial in the nuclear sector, and cask design and analysis are crucial for maintaining fuel integrity. Peak cladding temperature (PCT) is a significant factor in fuel failure likelihood. This research provides a thorough approach to designing and analysing nuclear transportation casks, focusing on PCT. Advanced computer techniques are used in the study, which includes a number of variables including the thermal properties of the cask and external heat sources. In this work, a composite PCM made of polyethylene glycol (PEG) and octadecanol is employed to provide equal heat transfer. The proposed composite PCM is reinforced by (Carbon Nano Tubes) CNTs to ensure homogeneous heat conduction within the PCM particles. The thermal behaviour of the cask is simulated using ANSYS, which takes into consideration conduction, convection, and radiation heat transfer among other aspects. The PCT for spent fuel assemblies for light water reactors operating in helium settings with varying decay heat loads and temperature boundary circumstances was calculated using these simulations. Finally yet importantly, the outcome has been validated by comparison with related studies. |
| format | Article |
| id | doaj-art-1165bff0dbc84338ab75ed72f1c653b3 |
| institution | Kabale University |
| issn | 1846-6168 1848-5588 |
| language | English |
| publishDate | 2025-01-01 |
| publisher | University North |
| record_format | Article |
| series | Tehnički Glasnik |
| spelling | doaj-art-1165bff0dbc84338ab75ed72f1c653b32025-02-06T15:28:42ZengUniversity NorthTehnički Glasnik1846-61681848-55882025-01-0119111011810.31803/tg-20231118075406Design and Analysis of Nuclear Transportation Cask Using Phase Changing MaterialGirish Venkatesh Gudi0R. G. Nagraj1Abhijit Dandavate2Department of Mechanical Engineering, Guru Nanak Dev Engineering College, Mailur Rd, Mailoor, Karnataka, Bidar 585403, IndiaGuru Nanak Dev Engineering College, Mailur Rd, Mailoor, Karnataka, Bidar 585403, IndiaDepartment of Automobile Engineering, Dhole Patil College of Engineering, 1284, Near Kharadi EON IT Prak, Dhole Patil College Road, Wagholi, Pune 412207, IndiaIn the nuclear sector, secure transportation of radioactive materials is crucial in the nuclear sector, and cask design and analysis are crucial for maintaining fuel integrity. Peak cladding temperature (PCT) is a significant factor in fuel failure likelihood. This research provides a thorough approach to designing and analysing nuclear transportation casks, focusing on PCT. Advanced computer techniques are used in the study, which includes a number of variables including the thermal properties of the cask and external heat sources. In this work, a composite PCM made of polyethylene glycol (PEG) and octadecanol is employed to provide equal heat transfer. The proposed composite PCM is reinforced by (Carbon Nano Tubes) CNTs to ensure homogeneous heat conduction within the PCM particles. The thermal behaviour of the cask is simulated using ANSYS, which takes into consideration conduction, convection, and radiation heat transfer among other aspects. The PCT for spent fuel assemblies for light water reactors operating in helium settings with varying decay heat loads and temperature boundary circumstances was calculated using these simulations. Finally yet importantly, the outcome has been validated by comparison with related studies.https://hrcak.srce.hr/file/473487ANSYSPeak Cladding Temperature (PCT)Phase Changing Material (PCM)transportation cask |
| spellingShingle | Girish Venkatesh Gudi R. G. Nagraj Abhijit Dandavate Design and Analysis of Nuclear Transportation Cask Using Phase Changing Material Tehnički Glasnik ANSYS Peak Cladding Temperature (PCT) Phase Changing Material (PCM) transportation cask |
| title | Design and Analysis of Nuclear Transportation Cask Using Phase Changing Material |
| title_full | Design and Analysis of Nuclear Transportation Cask Using Phase Changing Material |
| title_fullStr | Design and Analysis of Nuclear Transportation Cask Using Phase Changing Material |
| title_full_unstemmed | Design and Analysis of Nuclear Transportation Cask Using Phase Changing Material |
| title_short | Design and Analysis of Nuclear Transportation Cask Using Phase Changing Material |
| title_sort | design and analysis of nuclear transportation cask using phase changing material |
| topic | ANSYS Peak Cladding Temperature (PCT) Phase Changing Material (PCM) transportation cask |
| url | https://hrcak.srce.hr/file/473487 |
| work_keys_str_mv | AT girishvenkateshgudi designandanalysisofnucleartransportationcaskusingphasechangingmaterial AT rgnagraj designandanalysisofnucleartransportationcaskusingphasechangingmaterial AT abhijitdandavate designandanalysisofnucleartransportationcaskusingphasechangingmaterial |