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

Michael Podowski

关键词: BWR TYPE REACTORS;    COMPUTERIZED SIMULATION;    HEAT TRANSFER;    TWO-PHASE FLOW;    FLOW MODELS;    THERMAL HYDRAULICS;   

DOI  :  10.2172/968647
RP-ID  :  DOE/ID/14707
PID  :  OSTI ID: 968647
Others  :  TRN: US1001064

美国|英语

来源: SciTech Connect

【 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.