Abstract
To design a compact heat sink, a simplified geometry, enhanced heat dissipation, and the minimum pressure drop should be taken into consideration. With this objective, an experimental investigation has been conducted with the corrugated plate-fin heat sink by varying the relative radius of corrugation and relative corrugation pitch in the range of 0.16–0.31, and 0.06–0.16, respectively, for the Reynolds number range of 6000–14,000. Experiments were conducted on a corrugated plate-fin heat sink using an open-loop experimental system comprising a test section of a rectangular channel measuring 2300 mm long, 180 mm wide, and 80 mm high. The corrugated fin creates higher disturbances caused by multiple separations and reattachments in the flow and thereby yielding a higher localized heat transfer coefficient and enhanced heat transfer from the system. The maximum fin performance is found to be 5.87 for the corrugated plate-fin heat sink corresponding to the relative radius of corrugation and relative corrugation pitch of 0.16 and 0.125, respectively.
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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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Articles in the same Issue
- Frontmatter
- Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository
- Enhanced heat transfer in corrugated plate fin heat sink
- Discussion of options to increase the control drum worth in fast reactor
- New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV
- Computational analysis of nuclear desalination system under various configurations
- Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia
- Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS
- Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology
- Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions
- Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches
- Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications
- Modeling and simulation of deposited energy gain via irradiation of heavy ion beams on the fusion reactor contains spherical fuel capsules with foam
- Calendar of events