Empirical correlations for predicting the self-leveling behavior of debris bed  被引量:1

Empirical correlations for predicting the self-leveling behavior of debris bed

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作  者:CHENG Songbai YAMANO Hidemasa SUZUKI Tohru TOBITA Yoshiharu NAKAMURA Yuya ZHANG Bin MATSUMOTO Tatsuya MORITA Koji 

机构地区:[1]Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency (JAEA) [2]Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University

出  处:《Nuclear Science and Techniques》2013年第1期43-52,共10页核技术(英文)

基  金:Supported by an annual joint research project between Japan Atomic Energy Agency (JAEA) and Kyushu University

摘  要:Studies on the self-leveling behavior of debris bed are crucial for the assessment of core-disruptive accident (CDA) occurred in sodium-cooled fast reactors (SFR). To clarify this behavior over a comparatively wider range of gas velocities, a series of experiments were performed by injecting nitrogen gas uniformly from a pool bottom. Current experiments were conducted in a cylindrical tank, in which water, nitrogen gas and different kinds of solid particles, simulate the coolant, vapor (generated by coolant boiling) and fuel debris, respectively. Based on the quantitative data obtained (mainly the time variation of bed inclination angle), with the help of dimensional analysis technique, a set of empirical correlations to predict the self-leveling development depending on particle size, particle density and gas injection velocity was proposed and discussed. It was seen that good agreement could be obtained between the calculated and experimental values. Rationality of the correlations was further confirmed through detailed analyses of the effects of experimental parameters such as particle size, particle density, gas flow rate and boiling mode. In order to facilitate future analyses and simulations of CDAs in SFRs, the obtained results in this work will be utilized for the validations of an advanced fast reactor safety analysis code.Studies on the self-leveling behavior of debris bed are crucial for the assessment of core-disruptive accident (CDA) occurred in sodium-cooled fast reactors (SFR). To clarify this behavior over a comparatively wider range of gas velocities, a series of experiments were performed by injecting nitrogen gas uniformly from a pool bottom. Current experiments were conducted in a cylindrical tank, in which water, nitrogen gas and different kinds of solid particles, simulate the coolant, vapor (generated by coolant boiling) and fuel debris, respectively. Based on the quantitative data obtained (mainly the time variation of bed inclination angle), with the help of dimensional analysis technique, a set of empirical correlations to predict the self-leveling development depending on particle size, particle density and gas injection velocity was proposed and discussed. It was seen that good agreement could be obtained between the calculated and experimental values. Rationality of the correlations was further confirmed through detailed analyses of the effects of experimental parameters such as particle size, particle density, gas flow rate and boiling mode. In order to facilitate future analyses and simulations of CDAs in SFRs, the obtained results in this work will be utilized for the validations of an advanced fast reactor safety analysis code.

关 键 词:自流平 行为 模拟冷却水 预测 气体速度 注入氮气 粒子密度 实验值 

分 类 号:TL73[核科学技术—辐射防护及环境保护]

 

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