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NUFREQ-NP: A Computer Code for the Stability Analysis of Boiling Water Nuclear Reactors

S.J. Peng, M.Z. Podowski, Richard T. Lahey, Martin Becker

Open publisher page 28 citations

Abstract

The phenomena of nuclear coupled density-wave oscillations are of considerable importance in the stability analysis of boiling water nuclear reactors (BWRs). A state-of-the-art linear-frequency-domain digital computer code, NUFREQ-NP, has been developed for either forced- or natural-circulation BWR stability analysis. The NUFREQ-NP code can be excited by many external perturbations, including system pressure perturbation. It is based on one-dimensional drift-flux thermal hydraulics, and allows for subcooled boiling, arbitrary nonuniform axial and radial power shapes, distributed local losses (e.g., spacers), and detailed fuel element dynamics. NUFREQ-NP has been compared with the experimental data for the Peach Bottom-2 stability tests, and good agreement has been found.

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What this paper is about

The phenomena of nuclear coupled density-wave oscillations are of considerable importance in the stability analysis of boiling water nuclear reactors (BWRs). A state-of-the-art linear-frequency-domain digital computer code, NUFREQ-NP, has been developed for either forced- or natural-circulation BWR stability analysis. The NUFREQ-NP code can be excited by many external perturbations, including system pressure perturbation. It is based on one-dimensional drift-flux thermal hydraulics, and allows for subcooled boiling, arbitrary nonuniform axial and radial power shapes, distributed local losses (e.g., spacers), and detailed fuel element dynamics. NUFREQ-NP has been compared with the experimental data for the Peach Bottom-2 stability tests, and good agreement has been found.

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Available abstract

The phenomena of nuclear coupled density-wave oscillations are of considerable importance in the stability analysis of boiling water nuclear reactors (BWRs). A state-of-the-art linear-frequency-domain digital computer code, NUFREQ-NP, has been developed for either forced- or natural-circulation BWR stability analysis. The NUFREQ-NP code can be excited by many external perturbations, including system pressure perturbation. It is based on one-dimensional drift-flux thermal hydraulics, and allows for subcooled boiling, arbitrary nonuniform axial and radial power shapes, distributed local losses (e.g., spacers), and detailed fuel element dynamics. NUFREQ-NP has been compared with the experimental data for the Peach Bottom-2 stability tests, and good agreement has been found.

Key concepts: Boiling, Boiling water reactor, Nuclear engineering, Code (set theory), Nuclear reactor, Stability (learning theory), Computer science, Physics

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