NUFREQ-NP: a digital computer code for the linear stability analysis of boiling water nuclear reactors
Technical Report
·
OSTI ID:5327664
The phenomena of nuclear-coupled density-wave oscillations are of considerable importance in boiling water nuclear reactor (BWR) stability analysis. 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), point or multi-dimensional neutron kinetics, and detailed fuel element dynamics. It has been compared with both out-of-core and in-core data, and good agreement has been found.
- Research Organization:
- Rensselaer Polytechnic Inst., Troy, NY (USA)
- OSTI ID:
- 5327664
- Report Number(s):
- NUREG/CR-4116; ON: TI85902159
- Country of Publication:
- United States
- Language:
- English
Similar Records
NUFREQ-NP, a digital computer code for the linear stability analysis of boiling water nuclear reactors
NUFREQ-NP: a computer code for the stability analysis of boiling water nuclear reactors
Development of NUFREQ-N, an analytical model for the stability analysis of nuclear coupled density-wave oscillations in boiling water nuclear reactors
Thesis/Dissertation
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:5817600
NUFREQ-NP: a computer code for the stability analysis of boiling water nuclear reactors
Journal Article
·
Wed Oct 31 23:00:00 EST 1984
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:6030330
Development of NUFREQ-N, an analytical model for the stability analysis of nuclear coupled density-wave oscillations in boiling water nuclear reactors
Thesis/Dissertation
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6136312
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
MECHANICS
N CODES
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR KINETICS
REACTOR STABILITY
REACTORS
STABILITY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
MECHANICS
N CODES
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR KINETICS
REACTOR STABILITY
REACTORS
STABILITY
WATER COOLED REACTORS
WATER MODERATED REACTORS