Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental Interpretation
Thermally insulated concretes are a type of alternative building material that helps improve thermal efficiency in nuclear reactor vault safety vessel applications. The experimental results of thermal conductivity values of lightweight concrete materials at various temperatures are presented in this...
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| Main Authors: | , , , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2022-01-01
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| Series: | Advances in Materials Science and Engineering |
| Online Access: | http://dx.doi.org/10.1155/2022/4493910 |
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| author | M. Anish T. Arunkumar J. Jayaprabakar Sami Al Obaid Saleh Alfarraj M. M. Raj Assefa Belay |
| author_facet | M. Anish T. Arunkumar J. Jayaprabakar Sami Al Obaid Saleh Alfarraj M. M. Raj Assefa Belay |
| author_sort | M. Anish |
| collection | DOAJ |
| description | Thermally insulated concretes are a type of alternative building material that helps improve thermal efficiency in nuclear reactor vault safety vessel applications. The experimental results of thermal conductivity values of lightweight concrete materials at various temperatures are presented in this paper. To minimize heat conduction in concrete, different lightweight aggregates and vermiculite are employed as coarse aggregate alternatives.Both linear and plane heat source approaches are used to calculate the thermal conductivity values of the specimens. The findings emphasize that increasing the proportion of lightweight particles in concrete may dramatically lower the thermal conductivity, with the kind of lightweight aggregates having a vital role in thermal insulation. The inclusion of micron-sized vermiculite decreases heat conductivity even further; however, the effect is less obvious than that of lightweight particles. |
| format | Article |
| id | doaj-art-17b5f92531f5407685a839335e162326 |
| institution | Kabale University |
| issn | 1687-8442 |
| language | English |
| publishDate | 2022-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Advances in Materials Science and Engineering |
| spelling | doaj-art-17b5f92531f5407685a839335e1623262025-02-03T06:11:54ZengWileyAdvances in Materials Science and Engineering1687-84422022-01-01202210.1155/2022/4493910Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental InterpretationM. Anish0T. Arunkumar1J. Jayaprabakar2Sami Al Obaid3Saleh Alfarraj4M. M. Raj5Assefa Belay6School of Mechanical EngineeringDepartment of Mechanical EngineeringSchool of Mechanical EngineeringDepartment of Botany and MicrobiologyZoology DepartmentDepartment of Mechatronics EngineeringDepartment of Mechanical EngineeringThermally insulated concretes are a type of alternative building material that helps improve thermal efficiency in nuclear reactor vault safety vessel applications. The experimental results of thermal conductivity values of lightweight concrete materials at various temperatures are presented in this paper. To minimize heat conduction in concrete, different lightweight aggregates and vermiculite are employed as coarse aggregate alternatives.Both linear and plane heat source approaches are used to calculate the thermal conductivity values of the specimens. The findings emphasize that increasing the proportion of lightweight particles in concrete may dramatically lower the thermal conductivity, with the kind of lightweight aggregates having a vital role in thermal insulation. The inclusion of micron-sized vermiculite decreases heat conductivity even further; however, the effect is less obvious than that of lightweight particles.http://dx.doi.org/10.1155/2022/4493910 |
| spellingShingle | M. Anish T. Arunkumar J. Jayaprabakar Sami Al Obaid Saleh Alfarraj M. M. Raj Assefa Belay Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental Interpretation Advances in Materials Science and Engineering |
| title | Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental Interpretation |
| title_full | Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental Interpretation |
| title_fullStr | Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental Interpretation |
| title_full_unstemmed | Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental Interpretation |
| title_short | Thermal Conductivity of Thermally Insulated Concretes in a Nuclear Safety Vessel of Reactor Vault: Experimental Interpretation |
| title_sort | thermal conductivity of thermally insulated concretes in a nuclear safety vessel of reactor vault experimental interpretation |
| url | http://dx.doi.org/10.1155/2022/4493910 |
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