Prediction method of critical power by film flow rate measurement and subchannel analysis

Miyuki Akiba, Tomoji Takamasa, Shinichi Morooka

研究成果: Article

2 引用 (Scopus)

抄録

This paper presents a method that can estimate the critical power of boiling water reactors, BWRs, with regard to spacer geometry. The current experimental method for estimating the critical power for BWR design requires many trained experts and expensive facilities to conduct the experiments. In the present method, the liquid film flow rate of adiabatic gas-liquid two-phase flow and a subchannel analysis of the actual BWR flow condition are measured experimentally and analyzed. In the experiment, deposition enhancement coefficients of three spacer geometries-a ferrule, an egg-crate, and a ferrule spacer with twisted tape (CYCLONE spacer)-were estimated by measuring the liquid film flow rate of air-water two-phase flow flowing up in a vertical square (4×4) rod bundle that simulated the rod bundle of a BWR. Using these coefficients, the critical powers for bundles using each type of spacer geometry were calculated in the subchannel analysis. This method was validated using previous critical power data in the actual BWR flow condition. The critical powers predicted by this method agreed well with those of the experimental data. The result confirmed the effectiveness of this experiment-simulation combined method, as well as the advantage over current experimental methods in terms of human and facility costs.

元の言語English
ページ(範囲)309-323
ページ数15
ジャーナルHeat Transfer - Asian Research
34
発行部数5
DOI
出版物ステータスPublished - 2005 7
外部発表Yes

Fingerprint

spacers
flow velocity
Flow rate
Liquid films
Two phase flow
Geometry
bundles
predictions
two phase flow
Boiling water reactors
Experiments
rods
Tapes
liquids
geometry
boiling water reactors
Gases
eggs
coefficients
Water

ASJC Scopus subject areas

  • Fluid Flow and Transfer Processes

これを引用

Prediction method of critical power by film flow rate measurement and subchannel analysis. / Akiba, Miyuki; Takamasa, Tomoji; Morooka, Shinichi.

:: Heat Transfer - Asian Research, 巻 34, 番号 5, 07.2005, p. 309-323.

研究成果: Article

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AB - This paper presents a method that can estimate the critical power of boiling water reactors, BWRs, with regard to spacer geometry. The current experimental method for estimating the critical power for BWR design requires many trained experts and expensive facilities to conduct the experiments. In the present method, the liquid film flow rate of adiabatic gas-liquid two-phase flow and a subchannel analysis of the actual BWR flow condition are measured experimentally and analyzed. In the experiment, deposition enhancement coefficients of three spacer geometries-a ferrule, an egg-crate, and a ferrule spacer with twisted tape (CYCLONE spacer)-were estimated by measuring the liquid film flow rate of air-water two-phase flow flowing up in a vertical square (4×4) rod bundle that simulated the rod bundle of a BWR. Using these coefficients, the critical powers for bundles using each type of spacer geometry were calculated in the subchannel analysis. This method was validated using previous critical power data in the actual BWR flow condition. The critical powers predicted by this method agreed well with those of the experimental data. The result confirmed the effectiveness of this experiment-simulation combined method, as well as the advantage over current experimental methods in terms of human and facility costs.

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