Development of a Solver for Multi-Fluid and Multi-Pressure Model

Author:

Zhang Hao123ORCID,Yang Yanhua123

Affiliation:

1. Shanghai Jiao Tong University, School of Nuclear Science and Engineering, 800 Dong Chuan Road, Shanghai 200240, China

2. State Power Investment Corporation Research Institute, Future Science and Technology City, South Park, Beijing 102209, China

3. National Energy Key Laboratory of Nuclear Power Software, Future Science and Technology City, South Park, Beijing 102209, China

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. M. J. THURGOOD et al. “COBRA/TRAC—A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems: Equations and Constitutive Models,” NUREG/CR-3046, PNL-4385, Vol. 1, Rev. 4, Pacific Northwest Laboratory (1983).

2. Characteristics, Stability, and Short-Wavelength Phenomena in Two-Phase Flow Equation Systems

3. Characteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations and Their Finite Difference Approximations

4. One-dimensional two-fluid equations for horizontal stratified two-phase flow

5. One-dimensional models for transient gas-liquid flows in ducts

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