A Simple Approach to the Prediction of Transient Self-Leveling Behavior of Debris Bed
During a postulated core disruptive accident (CDA) in a sodium-cooled fast reactor (SFR), over the core-support structure and/or in the lower inlet plenum of the reactor vessel there is the possibility of the formation of conically-shaped debris bed. However, coolant boiling may lead ultimately to leveling of the debris bed. In this study, to clarify this behavior, a series of experiments was performed by percolating nitrogen gas uniformly through particle beds. Wide ranges of experimental parameters were used, including particle diameter (from 0.4 mm to 6 mm), particle density (beads made of glass, alumina and zirconia) and gas flow rate (from around 0.5 L/min to around 8 L/min). Based on the experimental data obtained, a simple empirical approach was suggested to evaluate the transient variation in the bed inclination angle during the leveling. Comparative analyses between the model-based and experimental data have convincingly demonstrated the efficiency of the proposed approach given the current range of experimental conditions. Validation of this approach was confirmed through analyses of the effects of experimental parameters, while its applicability to extended conditions (different initial inclination angles) was further validated by several typical experimental cases.
sodium-cooled fast reactor core disruptive accident self-leveling debris bed empirical correlation
Songbai CHENG Hirotaka TAGAMI Tohru SUZUKI Yoshiharu TOBITA Takayuki KAI Yoji GONDAI Yuya NAKAMURA Fusata FUKE Bin ZHANG Tatsuya MATSUMOTO Koji MORITA Hidemasa YAMANO
Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nish Advanced Nuclear System R&D Directorate, Japan Atomic Energy Agency,4002 Narita, O-arai, Ibaraki 311
国际会议
4th International Symposium on Heat Transfer and Energy Conservation(第四届传热与节能国际研讨会 ISHTEC2012)
广州
英文
1-5
2012-01-06（万方平台首次上网日期，不代表论文的发表时间）