Comparative analysis of compact heat exchangers for application as the intermediate heat exchanger for advanced nuclear reactors
- Univ. of Idaho, Moscow, ID (United States)
- The Ohio State Univ., Columbus, OH (United States)
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
A comparative evaluation of alternative compact heat exchanger designs for use as the intermediate heat exchanger in advanced nuclear reactor systems is presented in this article. Candidate heat exchangers investigated included the Printed circuit heat exchanger (PCHE) and offset strip-fin heat exchanger (OSFHE). Both these heat exchangers offer high surface area to volume ratio (a measure of compactness [m2/m3]), high thermal effectiveness, and overall low pressure drop. Helium–helium heat exchanger designs for different heat exchanger types were developed for a 600 MW thermal advanced nuclear reactor. The wavy channel PCHE with a 15° pitch angle was found to offer optimum combination of heat transfer coefficient, compactness and pressure drop as compared to other alternatives. The principles of the comparative analysis presented here will be useful for heat exchanger evaluations in other applications as well.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1188614
- Alternate ID(s):
- OSTI ID: 1250060
- Report Number(s):
- INL/JOU-15-35644; TRN: US1500527
- Journal Information:
- Annals of Nuclear Energy (Oxford), Vol. 81; ISSN 0306-4549
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
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journal | January 2020 |
Heat Transfer and Pressure Drop Characteristics in Straight Microchannel of Printed Circuit Heat Exchangers
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journal | May 2015 |
The volume-based properties for dimensional analysis of micro heat exchanger
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journal | August 2019 |
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