Abstract
This study presents steam condensation scaled experiments and semi-empirical models in presence of nitrogen--a noncondensable gas (NCG), simulating air in the reactor containment--to support water-cooled small modular reactors (SMRs) passive containment cooling system (PCCS) design and analysis. Previous experimental studies on PCCS are focused on fixed and smaller tube (mostly 2-in.) geometries and specific test condition variations, bringing challenges with geometric scaling and mismatching with SMR prototypic design. To address these challenges, this study presents steam condensation test dataset obtained from three scaled test sections of 1-, 2-, and 4-in.-diameter steam condensers with an annular/jacket cooling of 2-, 3-, and 6 in.-diameter tubes, respectively. Test data were collected for steam ranges from 58 to 63 kg/hr., and NCG flow of 4.4 to 13.3 kg/hr. Annular cooling water flow was varied to obtain required testing conditions of saturated steam inlet and fully condensed outlet. Axial temperature test data of bulk cooling water, steam and condensate were collected by thermocouples for three test sections and various steam-NCG mixing/testing conditions. A standard data reduction method was adopted--utilizing iterative and nodalized mass and heat transfer calculation to estimate axial local heat fluxes, heat transfer coefficients (HTCs), condensation rates, film thickness, and Nusselt number. Based on the obtained dataset semi-empirical model results--a ratio of experimental and Nusselt's theoretical HTC are presented. Such results and findings are supportive of developing scaled-up testing facility, to enable model validations and accelerate next generation of reactors development and deployment.
| Original language | English |
|---|---|
| State | Published - 2024 |
| Event | Pacific Basin Nuclear Conference 2024 - Idaho Falls, United States Duration: Oct 7 2024 → Oct 10 2024 |
Conference
| Conference | Pacific Basin Nuclear Conference 2024 |
|---|---|
| Country/Territory | United States |
| City | Idaho Falls |
| Period | 10/7/24 → 10/10/24 |
Keywords
- 21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
- 42 - ENGINEERING
- 46 - INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
- 47 - OTHER INSTRUMENTATION
- 97 - MATHEMATICS AND COMPUTING
- Steam condensation
- scaled experiment
- non-condensable gas
- passive safety analysis
INL Publication Number
- INL/CON-24-81152
- 187702
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