Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor

Bhowmik, Palash Kumar; Sabharwall, Piyush; Johnson, Justin T.; Tano Retamales, Mauricio Eduardo; Wang, Congjian; O'Brien, J.E.; Lietwiler, Clay; Wu, Qiao

doi:10.1016/j.nucengdes.2024.113235

Title: Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor

Journal Article · 26 April 2024 · Nuclear Engineering and Design

DOI: https://doi.org/10.1016/j.nucengdes.2024.113235 · OSTI ID:2352282

Bhowmik, Palash Kumar ^[1];

^[1]; Johnson, Justin T. ^[1];

^[1];

^[1]; O'Brien, J.E. ^[1]; Lietwiler, Clay ^[2]; Wu, Qiao ^[3]

Idaho National Laboratory (INL), Idaho Falls, ID (United States). Reactor System Design and Analysis Division
Holtec International, Camden, NJ (United States)
Oregon State University, Corvallis, OR (United States)

Small modular reactors (SMRs) represent a promising option for providing clean and sustainable energy due to their potential for enhanced safety, reduced capital costs, and increased siting flexibility. However, new reactor systems require the development and operation of representative scaled-down test facilities to support the verification and validation of system computer codes and models. Here this study reviews the research on scaling methodologies and similarity principles pivotal in developing non-nuclear integral effects test and separate effects test facilities for water-cooled SMRs. The study focuses on a review of the scaling methods, similarity approaches, and possible challenges posed by the unique and compact design features of integral-pressurized water reactor-type SMRs, and their representative test facilities. This study also reviews previous research related to scaling and similarity methodologies and provides insights into design considerations for achieving prototypic conditions in test facilities. The findings and recommendations emphasize the broader impact of appropriate scaling and similarity principles to ensure meaningful and transferable results from non-nuclear test facilities to accelerate the safe and efficient deployment of next-generation water-cooled SMRs.

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

Sponsoring Organization:: USDOE Office of Science (SC)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2352282

Report Number(s):: INL/JOU-24-77870-Rev000

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: 2024 Vol. 424; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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