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

Quan Zhou, Rizwan Uddin

Research output: ResearchConference contribution

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.

LanguageEnglish (US)
Title of host publicationInternational Conference on Nuclear Engineering, Proceedings, ICONE
Pages855-862
Number of pages8
Volume4
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

Fingerprint

Hot Temperature
Hopf bifurcation
Neutrons
Kinetics
Control rods
Enthalpy
Temperature distribution
Steam
Polynomials

ASJC Scopus subject areas

  • Engineering(all)
  • Energy(all)

Cite this

Zhou, Q., & Uddin, R. (2002). Bifurcation analysis of nuclear-coupled thermal hydraulics of BWR using BIFDD. In International Conference on Nuclear Engineering, Proceedings, ICONE (Vol. 4, pp. 855-862). DOI: 10.1115/ICONE10-22680

Bifurcation analysis of nuclear-coupled thermal hydraulics of BWR using BIFDD. / Zhou, Quan; Uddin, Rizwan.

International Conference on Nuclear Engineering, Proceedings, ICONE. Vol. 4 2002. p. 855-862.

Research output: ResearchConference contribution

Zhou, Q & Uddin, R 2002, Bifurcation analysis of nuclear-coupled thermal hydraulics of BWR using BIFDD. in International Conference on Nuclear Engineering, Proceedings, ICONE. vol. 4, pp. 855-862, 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, United States, 4/14/02. DOI: 10.1115/ICONE10-22680
Zhou Q, Uddin R. Bifurcation analysis of nuclear-coupled thermal hydraulics of BWR using BIFDD. In International Conference on Nuclear Engineering, Proceedings, ICONE. Vol. 4. 2002. p. 855-862. Available from, DOI: 10.1115/ICONE10-22680
Zhou, Quan ; Uddin, Rizwan. / Bifurcation analysis of nuclear-coupled thermal hydraulics of BWR using BIFDD. International Conference on Nuclear Engineering, Proceedings, ICONE. Vol. 4 2002. pp. 855-862
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