Numerical Simulation of Departure from Nucleate Boiling in Rod Bundles under High-Pressure Conditions
In subcooled boiling flows beyond a certain heat flux, heat transfer is hampered due to a phenomenon known as Departure from Nucleate Boiling (DNB). Conducting DNB experiments at one-to-one nuclear reactor operating conditions is highly challenging and expensive. Another alternative approach is to u...
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Published in: | Fluids (Basel) Vol. 7; no. 2; p. 83 |
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Abstract | In subcooled boiling flows beyond a certain heat flux, heat transfer is hampered due to a phenomenon known as Departure from Nucleate Boiling (DNB). Conducting DNB experiments at one-to-one nuclear reactor operating conditions is highly challenging and expensive. Another alternative approach is to use Look-up table data. However, its applicability is limited due to its dependence on rod bundle correction factors. In the present investigation, a state-of-the-art Eulerian-Eulerian two-fluid model coupled with an extended heat flux partitioning model is used to predict DNB in tubes and rod bundles with square and hexagonal lattices (relevant to Pressurized Water Reactors). In this approach, bubble departure characteristics are modeled using semi-mechanistic models based on force balance analysis. The predicted DNB values are compared with experimental and Look-up table data and found out to be within 1.8% to 20%. |
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AbstractList | In subcooled boiling flows beyond a certain heat flux, heat transfer is hampered due to a phenomenon known as Departure from Nucleate Boiling (DNB). Conducting DNB experiments at one-to-one nuclear reactor operating conditions is highly challenging and expensive. Another alternative approach is to use Look-up table data. However, its applicability is limited due to its dependence on rod bundle correction factors. In the present investigation, a state-of-the-art Eulerian-Eulerian two-fluid model coupled with an extended heat flux partitioning model is used to predict DNB in tubes and rod bundles with square and hexagonal lattices (relevant to Pressurized Water Reactors). In this approach, bubble departure characteristics are modeled using semi-mechanistic models based on force balance analysis. The predicted DNB values are compared with experimental and Look-up table data and found out to be within 1.8% to 20%. |
Author | Vadlamudi, Sai Raja Gopal Nayak, Arun K. |
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CitedBy_id | crossref_primary_10_1115_1_4055071 crossref_primary_10_1016_j_anucene_2024_110427 crossref_primary_10_1016_j_nucengdes_2024_113310 crossref_primary_10_1016_j_physc_2024_1354548 |
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SubjectTerms | boiling in rod bundle departure from nucleate boiling DNB simulation Experiments Heat flux Heat transfer high-pressure DNB Lookup tables Mathematical models Nuclear reactors Nucleate boiling Pressurized water reactors Reactors rod bundle DNB Tubes Two fluid models |
Title | Numerical Simulation of Departure from Nucleate Boiling in Rod Bundles under High-Pressure Conditions |
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