Development of NUFREQ-N, an analytical model for the stability analysis of nuclear coupled density-wave oscillations in boiling-water nuclear reactors

Technical Report · Fri Jul 01 04:00:00 EDT 1983

DOI:https://doi.org/10.2172/5970330· OSTI ID:5970330

Park, G. C.; Podowski, M.; Becker, M.; Lahey, Jr., R. T.

A state-of-the-art one-dimensional thermal-hydraulic model has been developed to be used for the linear analysis of nuclear-coupled density-wave oscillations in a boiling water nuclear reactor (BWR). The model accounts for phasic slip, distributed spacers, subcooled boiling, space/time-dependent power distributions and distributed heated wall dynamics. In addition to a parallel channel stability analysis, a detailed model was derived for the BWR loop analysis of both the natural and forced circulation modes of operation. In its final form, this model constitutes a multi-input, multi-output(MIMO) linear system, which features a general nodal neutron kinetics model. The computer implementation of this model, NUFREQ-N, was used for the parametric study of a typical BWR/4 and comparisons were made with existing in-core and out-of-core data. Also, NUFREQ-N was used to analyze the expected stability characteristics of a typical BWR/4.

• Research Organization: Rensselaer Polytechnic Inst., Troy, NY (USA). Dept. of Nuclear Engineering
• OSTI ID: 5970330
• Report Number(s): NUREG/CR-3375; ON: DE83902809
• Country of Publication: United States
• Language: English

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