Development of Mechanistic Modeling Capabilities for Local Neutronically-Coupled Flow-Induced Instabilities in Advanced Water-Cooled Reactors

Podowski, Michael

Rensselaer Polytechnic Institute

关键词: Heat Transfer;    Bwr Type Reactors;    Computerized Simulation;    Thermal Hydraulics;    Two-Phase Flow;   

DOI  :  10.2172/968647
RP-ID  :  DOE/ID/14707
RP-ID  :  FG07-05ID14707
RP-ID  :  968647

美国|英语

来源: UNT Digital Library

【 摘 要 】

The major research objectives of this project included the formulation of flow and heat transfer modeling framework for the analysis of flow-induced instabilities in advanced light water nuclear reactors such as boiling water reactors. General multifield model of two-phase flow, including the necessary closure laws. Development of neurton kinetics models compatible with the proposed models of heated channel dynamics. Formulation and encoding of complete coupled neutronics/thermal-hydraulics models for the analysis of spatially-dependent local core instabilities. Computer simulations aimed at testing and validating the new models of reactor dynamics.