Regional stability estimation of natural circulation BWRs using SIRIUS-N facility

Masahiro Furuya*, Fumio Inada, Tim H.J.J. Van der Hagen

*この研究の対応する著者

研究成果: Article査読

7 被引用数 (Scopus)

抄録

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 3.13GWt 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 sub-cooling, and the fuel rod time constant.

本文言語English
ページ(範囲)341-350
ページ数10
ジャーナルJournal of Nuclear Science and Technology
42
4
DOI
出版ステータスPublished - 2005 4
外部発表はい

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学

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