Application of high-order numerical schemes and Newton-Krylov method to two-phase drift-flux model

Zou, Ling; Zhao, Haihua; Zhang, Hongbin

doi:10.1016/j.pnucene.2017.07.008

Title: Application of high-order numerical schemes and Newton-Krylov method to two-phase drift-flux model

Journal Article · Mon Aug 07 00:00:00 EDT 2017 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2017.07.008· OSTI ID:1375246

^[1]; Zhao, Haihua ^[1]; Zhang, Hongbin ^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)

This study concerns the application and solver robustness of the Newton-Krylov method in solving two-phase flow drift-flux model problems using high-order numerical schemes. In our previous studies, the Newton-Krylov method has been proven as a promising solver for two-phase flow drift-flux model problems. However, these studies were limited to use first-order numerical schemes only. Moreover, the previous approach to treating the drift-flux closure correlations was later revealed to cause deteriorated solver convergence performance, when the mesh was highly refined, and also when higher-order numerical schemes were employed. In this study, a second-order spatial discretization scheme that has been tested with two-fluid two-phase flow model was extended to solve drift-flux model problems. In order to improve solver robustness, and therefore efficiency, a new approach was proposed to treating the mean drift velocity of the gas phase as a primary nonlinear variable to the equation system. With this new approach, significant improvement in solver robustness was achieved. With highly refined mesh, the proposed treatment along with the Newton-Krylov solver were extensively tested with two-phase flow problems that cover a wide range of thermal-hydraulics conditions. Satisfactory convergence performances were observed for all test cases. Numerical verification was then performed in the form of mesh convergence studies, from which expected orders of accuracy were obtained for both the first-order and the second-order spatial discretization schemes. Finally, the drift-flux model, along with numerical methods presented, were validated with three sets of flow boiling experiments that cover different flow channel geometries (round tube, rectangular tube, and rod bundle), and a wide range of test conditions (pressure, mass flux, wall heat flux, inlet subcooling and outlet void fraction).

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Research Organization:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1375246

Alternate ID(s):: OSTI ID: 1549808

Report Number(s):: INL/JOU-17-40865; PII: S0149197017301750

Journal Information:: Progress in Nuclear Energy, Vol. 100; ISSN 0149-1970

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 5 works

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