TY - JOUR
T1 - Characteristics of self-leveling behavior of debris beds in a series of experiments
AU - Cheng, Songbai
AU - Yamano, Hidemasa
AU - Suzuki, Tohru
AU - Tobita, Yoshiharu
AU - Nakamura, Yuya
AU - Zhang, Bin
AU - Matsumoto, Tatsuya
AU - Morita, Koji
N1 - Funding Information:
This work was supported by several annual joint research projects between Japan Atomic Energy Agency (JAEA) and Kyushu University. The experiments involved in this work were mainly performed using the facilities in Kyushu University.
PY - 2013
Y1 - 2013
N2 - During a hypothetical core-disruptive accident (CDA) in a sodium-cooled fast reactor (SFR), degraded core materials can form roughly conically-shaped debris beds over the core-support structure and/or in the lower inlet plenum of the reactor vessel from rapid quenching and fragmentation of the core material pool. However, coolant boiling may ultimately lead to leveling of the debris bed, which is crucial to the relocation of the molten core and heat-removal capability of the debris bed. To clarify the mechanisms underlying this self-leveling behavior, a large number of experiments were performed within a variety of conditions in recent years, under the constructive collaboration between the Japan Atomic Energy Agency (JAEA) and Kyushu University (Japan). The present contribution synthesizes and gives detailed comparative analyses of those experiments. Effects of various experimental parameters that may have potential influence on the leveling process, such as boiling mode, particle size, particle density, particle shape, bubbling rate, water depth and column geometry, were investigated, thus giving a large palette of favorable data for the better understanding of CDAs, and improved verifications of computer models developed in advanced fast reactor safety analysis codes.
AB - During a hypothetical core-disruptive accident (CDA) in a sodium-cooled fast reactor (SFR), degraded core materials can form roughly conically-shaped debris beds over the core-support structure and/or in the lower inlet plenum of the reactor vessel from rapid quenching and fragmentation of the core material pool. However, coolant boiling may ultimately lead to leveling of the debris bed, which is crucial to the relocation of the molten core and heat-removal capability of the debris bed. To clarify the mechanisms underlying this self-leveling behavior, a large number of experiments were performed within a variety of conditions in recent years, under the constructive collaboration between the Japan Atomic Energy Agency (JAEA) and Kyushu University (Japan). The present contribution synthesizes and gives detailed comparative analyses of those experiments. Effects of various experimental parameters that may have potential influence on the leveling process, such as boiling mode, particle size, particle density, particle shape, bubbling rate, water depth and column geometry, were investigated, thus giving a large palette of favorable data for the better understanding of CDAs, and improved verifications of computer models developed in advanced fast reactor safety analysis codes.
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U2 - 10.5516/NET.02.2012.068
DO - 10.5516/NET.02.2012.068
M3 - Article
AN - SCOPUS:84879457262
SN - 1738-5733
VL - 45
SP - 323
EP - 334
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
IS - 3
ER -