A robust mechanistic approach to prediction of departure from nucleate boiling

Xingang Zhao, Koroush Shirvan, Robert K. Salko

Research output: Contribution to conferencePaperpeer-review

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 languageEnglish
Pages785-794
Number of pages10
StatePublished - 2020
Event14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States
Duration: Sep 22 2019Sep 27 2019

Conference

Conference14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
Country/TerritoryUnited States
CitySeattle
Period09/22/1909/27/19

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.

FundersFunder number
Consortium for Advanced Simulation of Light Water Reactors
U.S. Department of Energy

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