National Technical Reports Library

The National Technical Information Service acquires, indexes, abstracts, and archives the largest collection of U.S. government-sponsored technical reports in existence. The NTRL offers online, free and open access to these authenticated government technical reports. Technical reports and documents in its repository may be available online for free either from the issuing federal agency, the U.S. Government Publishing Office’s Federal Digital System website, or through search engines.

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Nuclear-Coupled Flow Instabilities and Their Effects on Dryout.

DE2005832996

Publication Date	2004
Personal Author	Ishii, M.; Sun, X.; Kuran, S.
Page Count	196
Abstract	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.
Keywords	BWR type reactors Instability Two-phase flow Dryout Computerized simulation Classification Oscillations
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Purdue Univ., West Lafayette, IN. School of Nuclear Engineering.; Department of Energy, Nuclear Engineering Education and Research Program,
Supplemental Notes	Sponsored by Department of Energy, Nuclear Engineering Education and Research Program, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200524

Nuclear-Coupled Flow Instabilities and Their Effects on Dryout.

Nuclear-Coupled Flow Instabilities and Their Effects on Dryout.
DE2005832996

Publication Date	2004
Personal Author	Ishii, M.; Sun, X.; Kuran, S.
Page Count	196
Abstract	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.
Keywords	BWR type reactors Instability Two-phase flow Dryout Computerized simulation Classification Oscillations
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Purdue Univ., West Lafayette, IN. School of Nuclear Engineering.; Department of Energy, Nuclear Engineering Education and Research Program,
Supplemental Notes	Sponsored by Department of Energy, Nuclear Engineering Education and Research Program, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200524