Bifurcation analysis of nuclear-coupled thermal hydraulics of BWR using BIFDD

Quan Zhou, Rizwan Uddin

Research output: Contribution to conferencePaperpeer-review

Abstract

Stability and bifurcation analyses of nuclear-coupled thermal hydraulic instability in BWR has been performed using a semi-analytical method. The BWR model used in this study consists of three parts: neutron kinetics, fuel rod heat conduction and single and two-phase heated channel thermal hydraulics. Point reactor model is currently being used for neutron kinetics and will be extended in the future to higher order lambda or omega-mode. In the heat conduction part, a piecewise quadratic approximation to radial temperature distribution in fuel pellet and cladding is assumed. ODEs for the expansion coefficients of the quadratic spatial profiles are developed by applying variational principle. Similar to the heat conduction model, the spatial enthalpy distribution in the single phase region and steam quality in the two-phase region in the BWR core are approximated by quadratic polynomials. Two-phase flow is modeled using the homogeneous equilibrium model. A bifurcation analysis code, BIFDD, is then used to perform the analysis for the stability boundary (SB) and the nature of Poincaré-Andronov-Hopf bifurcation (PAH-B). Results in control-rod-induced-reactivity-inlet-subcooling-number space show that both super or sub-critical bifurcation can occur along the SB-the subcritical bifurcation occurs for very small or very large subcooling number values; supercritical PAH-B occurs for intermediate values of subcooling number.

Original languageEnglish (US)
Pages855-862
Number of pages8
DOIs
StatePublished - 2002
Event10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA, United States
Duration: Apr 14 2002Apr 18 2002

Other

Other10th International Conference on Nuclear Engineering (ICONE 10)
CountryUnited States
CityArlington, VA
Period4/14/024/18/02

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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