Abstract
The critical heat flux (CHF) corresponding to the departure from nucleate boiling (DNB) is a regulatory limit for licensing of pressurized water reactors. Under DNB conditions, the heated surface is permanently blanketed by a vapor film, leading to a sharp deterioration of the heat transfer coefficient at the heater/coolant interface and an abrupt temperature rise. Unfortunately, the path for an accurate, robust prediction of DNB has been elusive due to lack of consensus on its triggering mechanism. This work reviews existing physics-driven modeling tools. An evolutionary channel-scale mechanistic model that leverages key assumptions in the relatively well-accepted mechanisms of liquid sublayer dryout and near-wall bubble crowding is then proposed. Detailed validation of the proposed model has demonstrated its improved predictive capabilities over previous data/physics-driven models for an extensive DNB-specific CHF test matrix covering a wide range of flow conditions. The unique feature of the proposed model lies in its ability to predict DNB without recalibration for different heater geometries (including round tube, annulus, and rod bundle), which is essential in deciphering fuel performance metrics from different facilities and reactor types. The proposed model will be implemented in fuel performance codes to help improve modeling of transient DNB scenarios such as during a reactivity-initiated accident.
Original language | English |
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Pages | 785-794 |
Number of pages | 10 |
State | Published - 2020 |
Event | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States Duration: Sep 22 2019 → Sep 27 2019 |
Conference
Conference | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 |
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Country/Territory | United States |
City | Seattle |
Period | 09/22/19 → 09/27/19 |
Funding
This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (CASL), an Energy Innovation Hub for modeling and simulation of nuclear reactors under the U.S. Department of Energy.
Funders | Funder number |
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Consortium for Advanced Simulation of Light Water Reactors | |
U.S. Department of Energy |