Design of separate-effects In-Pile transient boiling experiments at the $\mathrm{TREAT}$ Facility

Folsom, Charles P.; Armstrong, Robert J.; Woolstenhulme, Nicolas E.; Fleming, Austin D.; Hill, Connie M.; Jensen, Colby B.; Wachs, Daniel M.

doi:10.1016/j.nucengdes.2022.111919

Design of separate-effects In-Pile transient boiling experiments at the $$\mathrm{TREAT}$$ Facility

Journal Article · Mon Aug 15 00:00:00 EDT 2022 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2022.111919· OSTI ID:1957647

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Idaho National Laboratory (INL), Idaho Falls, ID (United States)

The cladding-to-coolant heat transfer during rapid power excursions, such as reactivity-initiated accidents, remains a crucial area of uncertainty in nuclear reactor safety. This uncertainty impacts the ability to accurately predict fuel performance behavior for these conditions. Improving our understanding of transient cladding-to-coolant heat transfer will enhance our ability to model design basis accidents and could increase design and improve safety margins for the current commercial fleet and advanced reactors. To address these issues, the Critical Heat Flux Static Environment Rodlet Transient Test Apparatus (CHF-SERTTA) experiment uses a novel approach with a borated stainless-steel heater rodlet that can replicate cladding temperatures experienced during a design-basis reactivity-initiated accident. The rodlet and experiment is instrumented to provide temperature and thermal-hydraulic conditions throughout the transient. The design of the rodlet allows for separate effect testing that eliminates complexities with a fuel and cladding specimen. We report the experiments have provided data that will be used to improve our understanding of boiling behavior, specifically critical heat flux, under transient conditions.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

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

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1957647

Report Number(s):: INL/JOU-22-65774

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: - Vol. 397; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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