Assessment of a compact steam generator aided by computational fluid dynamics
Name
1191905265-MIT.pdf
Size
1.6 MB
Format
Adobe PDF
Checksum (MD5)
f6d128b387706d394ab772094dc47f6d
Author(s)
Aranda Ocampo, Brandon Ariel.
Advisor(s)
Koroush Shirvan.
Date Issued
2020
Publisher
Massachusetts Institute of Technology
Abstract
Steam generators are an essential component in nuclear power plants which serve to transfer thermal power from a liquid coolant to steam by boiling water. Even with many advancements in the designs of steam generators, they still require extremely large sizes and have high costs which are major hurdles for the implementation of new reactor designs such as Small Modular Reactors. Using a Printed Circuit Heat Exchanger (PCHE) such as those from the company HeatricTM as a steam generator to boil the liquid in the secondary side has potential to overcome the disadvantages of conventional steam generators. Computational Fluid Dynamics was used to aid the assessment of such compact steam generator. The models used were bench marked against a 1-D MATLAB code which simulated a compact steam generator with straight, semi-circular channels. The same conditions were used to simulate a zig-zag, semi-circular PCHE. The zig-zag configuration resulted in a 22 °C increase in superheat over the straight channel configuration at the cost of pressure drops that are over 4 times higher but yet easily accommodated. The PCHE was also simulated in different orientations with respect to gravity and determined there is little advantage in using a vertical layout regarding pressure drop for the zig-zag configuration. Plugging of a single channel was also simulated to determine the effect on surrounding channels and potential hot spots.
Description
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, May, 2020
Cataloged from the official PDF of thesis.
Includes bibliographical references (pages 63-65).
Subjects
Nuclear Science and Engineering.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
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MIT theses may be protected by copyright. Please reuse MIT thesis content according to the MIT Libraries Permissions Policy, which is available through the URL provided.
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