Experimental investigations of Critical Heat Flux re-occurrence on post-CHF surfaces

He, Mingfu; Ali, Amir; Chen, Minghui

doi:10.1016/j.pnucene.2022.104211

Experimental investigations of Critical Heat Flux re-occurrence on post-CHF surfaces

Journal Article · Tue Apr 05 00:00:00 EDT 2022 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2022.104211· OSTI ID:1977583

He, Mingfu ^[1]; ^[2]; ^[3]

Univ. of New Mexico, Albuquerque, NM (United States); OSTI
Idaho State Univ., Idaho Falls, ID (United States)
Univ. of New Mexico, Albuquerque, NM (United States)

Under the extreme environments of light water reactors, the cladding materials demonstrate evolutionary transformations in terms of material compositions, surface morphologies, and thermal-physical properties. This study investigates how the temperature overshooting of Critical Heat Flux (CHF) affects the re-occurrence of CHF on the post-CHF surfaces. Experimental results reveal that the CHF difference between as-received and post-CHF surfaces can be significant, which depends on materials. CHF is enhanced on post-CHF Stainless Steel (SS 316) specimens while it deteriorates on post-CHF Inconel-600 specimens. In comparison with the as-received surfaces, the post-CHF surface of SS 316 is more hydrophobic, while Inconel 600 is more hydrophilic. The scanning electron microscope micrographs of post-CHF surfaces show that surface morphologies that are structured by oxide crystals are formed on SS 316 samples but not on Inconel 600 samples. The physical rationale behind the CHF difference could be boiling heat transfer conjugated with thermal-physical proprieties of investigated surface materials and surface morphologies features. In conclusion, the results imply that it is indispensable to bookkeep the evolutionary changes of cladding surface materials, especially for cladding candidates of Accident Tolerant Fuel since operation histories can leave footprints on cladding surfaces, thus resulting in CHF re-occurrence differences.

View Accepted Manuscript (DOE)

Research Organization:: Univ. of New Mexico, Albuquerque, NM (United States); Utah State Univ., Logan, UT (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: NE0008531; NE0008687

OSTI ID:: 1977583

Alternate ID(s):: OSTI ID: 1960879

Journal Information:: Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Journal Issue: C Vol. 148; ISSN 0149-1970

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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