Regional Stability Estimation of Natural Circulation BWRs using SIRIUS-N Facility
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概要
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The SIRIUS-N facility was designed and constructed for highly accurate simulation of core-wide and regional instabilities of the BWR. A real-time simulation was performed in the digital controller for heat conduction in a fuel-rod and modal point kinetics of reactor neutronics using measured void fractions in reactor core sections of the thermal-hydraulic loop. In order to estimate decay ratios, an auto-regressive method has been successfully applied for time series data of the core inlet flow rate. Experiments were conducted with the SIRIUS-N facility for the rated operating condition of 3.13 GWt natural circulation BWR. Channel and regional stability decay ratios were determined to be 0.38 and 0.54, respectively, which indicates sufficient margin for the instabilities. Experiments were extended to evaluate the stability sensitivity of design parameters such as the power profile, void reactivity coefficients, core inlet subcooling, and the fuel rod time constant.
- 2005-04-25
著者
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FURUYA Masahiro
Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry (CRIEP
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INADA Fumio
Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry (CRIEP
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VAN DER
Interfaculty Reactor Institute, Delft University of Technology
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Inada Fumio
Nuclear Technology Research Laboratory Central Research Institute Of Electric Power Industry (criepi
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Furuya Masahiro
Nuclear Technology Research Laboratory Central Research Institute Of Electric Power Industry (criepi
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Van Der
Interfaculty Reactor Institute Delft University Of Technology
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Furuya M
Central Res. Inst. Electrical Power Ind. Tokyo Jpn
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Furuya Masahiro
Nuclear Energy System Department, Central Research Institute of Electric Power Industry
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