Abstract
A heat pipe transfers heat effectively between two solid surfaces by incorporating the principles of the transition of phase and thermal conductivity. The study aims to investigate the thermal characteristics of a cylindrical heat pipe and the various factors affecting its performance. The effect of different working fluids, i.e., water, ethanol, and methanol, wick material, i.e., copper and stainless steel, and angle of inclination varied from varied between 0° and 90°. The fill volume is also varied from 20 to 40% to analyze the thermal resistance and effective thermal conductivity of the heat pipe. The optimum value of angle of inclination is found to be 60° at 30% fill volume of working fluid irrespective of the wick material.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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© 2022 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions
- Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
- Updating risk model for SGTR accident based on success criteria analysis
- The analysis of fire ignition frequency calculation for small modular light water reactors
- New flow boiling frictional pressure drop multipliers for smooth and microfin tubes
- Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading
- Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers
- The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface
- Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Calendar of events
Articles in the same Issue
- Frontmatter
- Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions
- Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
- Updating risk model for SGTR accident based on success criteria analysis
- The analysis of fire ignition frequency calculation for small modular light water reactors
- New flow boiling frictional pressure drop multipliers for smooth and microfin tubes
- Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading
- Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers
- The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface
- Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Calendar of events