TY - JOUR
T1 - Self-leveling onset criteria in debris beds
AU - Zhang, Bin
AU - Harada, Tetsushi
AU - Hirahara, Daisuke
AU - Matsumoto, Tatsuya
AU - Morita, Koji
AU - Fukuda, Kenji
AU - Yamano, Hidemasa
AU - Suzuki, Tohru
AU - Tobita, Yoshiharu
PY - 2010/4
Y1 - 2010/4
N2 - In a core-disruptive accident of a sodium-cooled fast breeder reactor, core debris may settle on the coresupport structure and/or in the lower inlet plenum of the reactor vessel because of rapid quenching and fragmentation of molten core materials in the subcooled sodium plenum. Coolant boiling is the mechanism driving the self-leveling of a debris bed that causes significant changes in the heat-removal capability of the beds. In the present study, we develop criteria establishing the onset of this self-leveling behavior that we base on a force balance model assuming a debris bed with a single-sized spherical particle. The model considers drag, buoyancy, and gravity acting on each particle. A series of experiments with simulant materials verified the applicability of this description of self-leveling. Particle size (between 0.5–6 mm), shape (spherical and nonspherical), density (namely of alumina, zirconia, lead, and stainless steel), along with boiling intensity, bed volume, and even experimental methods were taken into consideration to obtain general characteristics of the self-leveling process. We decided to use depressurization boiling to simulate an axially increasing void distribution in the debris bed, although bottom heating was also used to validate the use of the depressurization method. On the self-leveling onset issues, we obtained good agreement between model predictions and experimental results. Extrapolation of our model to actual reactor conditions is discussed.
AB - In a core-disruptive accident of a sodium-cooled fast breeder reactor, core debris may settle on the coresupport structure and/or in the lower inlet plenum of the reactor vessel because of rapid quenching and fragmentation of molten core materials in the subcooled sodium plenum. Coolant boiling is the mechanism driving the self-leveling of a debris bed that causes significant changes in the heat-removal capability of the beds. In the present study, we develop criteria establishing the onset of this self-leveling behavior that we base on a force balance model assuming a debris bed with a single-sized spherical particle. The model considers drag, buoyancy, and gravity acting on each particle. A series of experiments with simulant materials verified the applicability of this description of self-leveling. Particle size (between 0.5–6 mm), shape (spherical and nonspherical), density (namely of alumina, zirconia, lead, and stainless steel), along with boiling intensity, bed volume, and even experimental methods were taken into consideration to obtain general characteristics of the self-leveling process. We decided to use depressurization boiling to simulate an axially increasing void distribution in the debris bed, although bottom heating was also used to validate the use of the depressurization method. On the self-leveling onset issues, we obtained good agreement between model predictions and experimental results. Extrapolation of our model to actual reactor conditions is discussed.
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U2 - 10.1080/18811248.2010.9711969
DO - 10.1080/18811248.2010.9711969
M3 - Article
AN - SCOPUS:77950673938
SN - 0022-3131
VL - 47
SP - 384
EP - 395
JO - journal of nuclear science and technology
JF - journal of nuclear science and technology
IS - 4
ER -