Nuclear-Coupled Flow Instabilities and Their Effects on Dryout.

Ishii, M. ; Sun, X. ; Kuran, S.

Technical Information Center Oak Ridge Tennessee

关键词: BWR type reactors;    Instability;    Two-phase flow;    Dryout;    Computerized simulation;   

RP-ID  :  DE2005832996

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

Nuclear-coupled flow/power oscillations in boiling water reactors (BWRs) are investigated experimentally and analytically. A detailed literature survey is performed to identify and classify instabilities in two-phase flow systems. The classification and the identification of the leading physical mechanisms of the two-phase flow instabilities are important to propose appropriate analytical models and scaling criteria for simulation. For the purpose of scaling and the analysis of the nonlinear aspects of the coupled flow/power oscillations, an extensive analytical modeling strategy is developed and used to derive both frequency and time domain analysis tools.