NUFREQ-NP: a computer code for the stability analysis of boiling water nuclear reactors

Journal Article · Thu Nov 01 04:00:00 EST 1984 · Nucl. Sci. Eng.; (United States)

OSTI ID:6030330

Peng, S J; Becker, M; Lahey, R T; Podowski, M A

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.

• Research Organization: Rensselaer Polytechnic Inst., Troy, NY
• OSTI ID: 6030330
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 88:3; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BOILING
BWR TYPE REACTORS
COMPUTER CODES
CONVECTION
DISTURBANCES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
MASS TRANSFER
MECHANICS
N CODES
ONE-DIMENSIONAL CALCULATIONS
OSCILLATIONS
PEACH BOTTOM-2 REACTOR
PHASE TRANSFORMATIONS
POWER REACTORS
PRESSURE EFFECTS
REACTOR COMPONENTS
REACTORS
SPACERS
STABILITY
SUBCOOLED BOILING
THERMODYNAMICS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WAVE PROPAGATION