Development of a fully-consistent reduced order model to study instabilities in boiling water reactors

Dykin, V.; Demaziere, C.

Title: Development of a fully-consistent reduced order model to study instabilities in boiling water reactors

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Abstract

A simple nonlinear Reduced Order Model to study global, regional and local instabilities in Boiling Water Reactors is described. The ROM consists of three submodels: neutron-kinetic, thermal-hydraulic and heat-transfer models. The neutron-kinetic model allows representing the time evolution of the three first neutron kinetic modes: the fundamental, the first and the second azimuthal modes. The thermal-hydraulic model describes four heated channels in order to correctly simulate out-of-phase behavior. The coupling between the different submodels is performed via both void and Doppler feedback mechanisms. After proper spatial homogenization, the governing equations are discretized in the time-domain. Several modifications, compared to other existing ROMs, have been implemented, and are reported in this paper. One novelty of the ROM is the inclusion of both azimuthal modes, which allows to study combined instabilities (in-phase and out-of-phase), as well as to investigate the corresponding interference effects between them. The second modification concerns the precise estimation of so-called reactivity coefficients or C{sub mn}{sup *V,D} - coefficients by using direct cross-section data from SIMULATE-3 combined with the CORE SIM core simulator in order to calculate Eigenmodes. Furthermore, a non-uniform two-step axial power profile is introduced to simulate the separate heat production in the single and two-phase regions,more »« less

Authors:

Dykin, V.; Demaziere, C. ^[1]

Chalmers Univ. of Technology, Div. of Nuclear Engineering, Dept. of Applied Physics, SE-412 96 Gothenburg (Sweden)

Publication Date:: Sun Jul 01 00:00:00 EDT 2012

Research Org.:: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)

OSTI Identifier:: 22105593

Resource Type:: Conference

Resource Relation:: Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 14 refs.

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CROSS SECTIONS; DOPPLER EFFECT; FEEDBACK; FORSMARK-1 REACTOR; HEAT PRODUCTION; HEAT TRANSFER; INSTABILITY; ITERATIVE METHODS; KINETICS; NEUTRONS; NONLINEAR PROBLEMS; REACTIVITY COEFFICIENTS; REACTOR STABILITY; SIMULATION; THERMAL HYDRAULICS; TIME DEPENDENCE

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                    Dykin, V., and Demaziere, C. Development of a fully-consistent reduced order model to study instabilities in boiling water reactors.  United States: N. p., 2012. 
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                    Dykin, V., & Demaziere, C. Development of a fully-consistent reduced order model to study instabilities in boiling water reactors.  United States.

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                    Dykin, V., and Demaziere, C. 2012.  
        "Development of a fully-consistent reduced order model to study instabilities in boiling water reactors".  United States.

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@article{osti_22105593,

  title        = {Development of a fully-consistent reduced order model to study instabilities in boiling water reactors},

  author       = {Dykin, V. and Demaziere, C.},

  abstractNote = {A simple nonlinear Reduced Order Model to study global, regional and local instabilities in Boiling Water Reactors is described. The ROM consists of three submodels: neutron-kinetic, thermal-hydraulic and heat-transfer models. The neutron-kinetic model allows representing the time evolution of the three first neutron kinetic modes: the fundamental, the first and the second azimuthal modes. The thermal-hydraulic model describes four heated channels in order to correctly simulate out-of-phase behavior. The coupling between the different submodels is performed via both void and Doppler feedback mechanisms. After proper spatial homogenization, the governing equations are discretized in the time-domain. Several modifications, compared to other existing ROMs, have been implemented, and are reported in this paper. One novelty of the ROM is the inclusion of both azimuthal modes, which allows to study combined instabilities (in-phase and out-of-phase), as well as to investigate the corresponding interference effects between them. The second modification concerns the precise estimation of so-called reactivity coefficients or C{sub mn}{sup *V,D} - coefficients by using direct cross-section data from SIMULATE-3 combined with the CORE SIM core simulator in order to calculate Eigenmodes. Furthermore, a non-uniform two-step axial power profile is introduced to simulate the separate heat production in the single and two-phase regions, respectively. An iterative procedure was developed to calculate the solution to the coupled neutron-kinetic/thermal-hydraulic static problem prior to solving the time-dependent problem. Besides, the possibility of taking into account the effect of local instabilities is demonstrated in a simplified manner. The present ROM is applied to the investigation of an actual instability that occurred at the Swedish Forsmark-1 BWR in 1996/1997. The results generated by the ROM are compared with real power plant measurements performed during stability tests and show a good qualitative agreement. The present study provides some insight in a deeper understanding of the physical principles which drive both core-wide and local instabilities. (authors)},

  doi          = {},

  url          = {https://www.osti.gov/biblio/22105593},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sun Jul 01 00:00:00 EDT 2012},

  month        = {Sun Jul 01 00:00:00 EDT 2012}

}

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