EXPERIMENTAL INVESTIGATION OF MINIMUM FILM BOILING TEMPERATURE DURING REFLOOD TRANSIENTS

  • Turki K. Almudhhi
  • , Douglas J. Miller
  • , Grant R. Garrett
  • , Ian R. Lowery
  • , Fan Bill Cheung
  • , Brian R. Lowery
  • , Stephen M. Bajorek
  • , Kirk Tien
  • , Chris L. Hoxie

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Scopus citations

Abstract

Knowledge of the post-critical heat flux (post-CHF) heat transfer and accurate prediction of the boiling characteristics are important during nuclear safety assessments. The minimum film boiling temperature (Tmin) separates the film boiling regime and the transition boiling regime and its value is used to determine the boiling regime in thermal-hydraulics codes. In this study, the Tmin was investigated during constant reflood experiments under different flow conditions. Reflood experiments were performed at the NRC-PSU Rod Bundle Heat Transfer (RBHT) facility. The 7×7 bundle is electrically heated, and Inconel was used as the cladding material. Inverse heat conduction was used to determine the minimum film boiling temperature (Tmin) at different elevations in the bundle for a broad range of liquid subcooling and reflood rates. The liquid subcooling varied from 10 to 79 K (18 to 144 °F), whereas the flow rate ranged between 0.0254 m/s to 0.05 m/s (1 to 2 in/s). All experiments were conducted at 275 kPa (40 psi) pressure. The results show that under the same inlet conditions, Tmin varied with elevation. The flooding rate had a significant effect on Tmin, whereas liquid subcooling had a minor effect. At lower elevations of the rod bundle, Tmin tends to increase with increasing flooding rate and liquid subcooling. However, the effect of subcooling on Tmin at a higher elevation was found to be insignificant since the liquid would reach saturation temperature regardless of the inlet subcooling.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages1924-1934
Number of pages11
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023Aug 25 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period8/20/238/25/23

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Instrumentation

Fingerprint

Dive into the research topics of 'EXPERIMENTAL INVESTIGATION OF MINIMUM FILM BOILING TEMPERATURE DURING REFLOOD TRANSIENTS'. Together they form a unique fingerprint.

Cite this