TY - JOUR
T1 - Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code
AU - Morita, Koji
AU - Zhang, Shuai
AU - Koshizuka, Seiichi
AU - Tobita, Yoshiharu
AU - Yamano, Hidemasa
AU - Shirakawa, Noriyuki
AU - Inoue, Fusao
AU - Yugo, Hiroaki
AU - Naitoh, Masanori
AU - Okada, Hidetoshi
AU - Yamamoto, Yuichi
AU - Himi, Masashi
AU - Hirano, Etsujo
AU - Shimizu, Sensuke
AU - Oue, Masaya
N1 - Funding Information:
The present study was carried out within the task “R&D of the Next Generation Safety Analysis Methods for Fast Reactors with New Computational Science and Technology” entrusted from the Ministry of Education, Culture, Sports, Science and Technology of Japan. The computation was mainly carried out using the computer facilities at Research Institute for Information Technology, Kyushu University.
PY - 2011/12
Y1 - 2011/12
N2 - A five-year research project has been initiated in 2005 to develop a code based on the MPS (Moving Particle Semi-implicit) method for detailed analysis of key phenomena in core disruptive accidents (CDAs) of sodium-cooled fast reactors (SFRs). The code is named COMPASS (Computer Code with Moving Particle Semi-implicit for Reactor Safety Analysis). The key phenomena include (1) fuel pin failure and disruption, (2) molten pool boiling, (3) melt freezing and blockage formation, (4) duct wall failure, (5) low-energy disruptive core motion, (6) debris-bed coolability, and (7) metal-fuel pin failure. Validation study of COMPASS is progressing for these key phenomena. In this paper, recent COMPASS results of detailed analyses for the several key phenomena are summarized. Simulations of GEYSER and THEFIS experiments were performed for dispersion and freezing behaviors of molten materials in narrow flow channels. In particular, the latter experiment using melt-solid mixture is also related to fundamental behavior of low energy disruptive core. CABRI-TPA2 experiment was simulated for boiling behavior of molten core pool. Expected mechanism of heat transfer between molten fuel and steel mixture was reproduced by the simulation. Analyses of structural dynamics using elastoplastic mechanics and fracture criteria were performed for SCARABEE BE+3 and CABRI E7 experiments. These two analyses are especially focused on thermal and mechanical failure of steel duct wall and fuel pin, respectively. The present results demonstrate COMPASS will be useful to understand and clarify the key phenomena of CDAs in SFRs in details.
AB - A five-year research project has been initiated in 2005 to develop a code based on the MPS (Moving Particle Semi-implicit) method for detailed analysis of key phenomena in core disruptive accidents (CDAs) of sodium-cooled fast reactors (SFRs). The code is named COMPASS (Computer Code with Moving Particle Semi-implicit for Reactor Safety Analysis). The key phenomena include (1) fuel pin failure and disruption, (2) molten pool boiling, (3) melt freezing and blockage formation, (4) duct wall failure, (5) low-energy disruptive core motion, (6) debris-bed coolability, and (7) metal-fuel pin failure. Validation study of COMPASS is progressing for these key phenomena. In this paper, recent COMPASS results of detailed analyses for the several key phenomena are summarized. Simulations of GEYSER and THEFIS experiments were performed for dispersion and freezing behaviors of molten materials in narrow flow channels. In particular, the latter experiment using melt-solid mixture is also related to fundamental behavior of low energy disruptive core. CABRI-TPA2 experiment was simulated for boiling behavior of molten core pool. Expected mechanism of heat transfer between molten fuel and steel mixture was reproduced by the simulation. Analyses of structural dynamics using elastoplastic mechanics and fracture criteria were performed for SCARABEE BE+3 and CABRI E7 experiments. These two analyses are especially focused on thermal and mechanical failure of steel duct wall and fuel pin, respectively. The present results demonstrate COMPASS will be useful to understand and clarify the key phenomena of CDAs in SFRs in details.
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U2 - 10.1016/j.nucengdes.2011.03.038
DO - 10.1016/j.nucengdes.2011.03.038
M3 - Article
AN - SCOPUS:82555194210
SN - 0029-5493
VL - 241
SP - 4672
EP - 4681
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
IS - 12
ER -