TY - JOUR
T1 - 钠冷快堆碎片床迁移判据模型适用性分析
AU - Teng, Chunming
AU - Zhang, Bin
AU - Shan, Jianqiang
AU - Zhang, Xisi
AU - Cao, Yonggang
N1 - Publisher Copyright:
© 2021, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
PY - 2021/2/15
Y1 - 2021/2/15
N2 - When the core disruptive accident (CDA) occurs in the sodium-cooled fast reactor (SFR), the melted core fuel is cooled and solidified into debris particles by the coolant, which accumulates in the lower plenum and forms the debris bed. In order to effectively remove the decay heat from the debris bed and implement the in-vessel corium retention (IVR), it is necessary to predict and simulate the relocation behavior of the debris bed. For this reason, Zhang et al. developed an onset model for judging the relocation of the debris bed based on the force balance analysis of the particle. In this paper, a large number of debris bed relocation experiments were carried out by bottom gas-injection method, and the relocation onset model was used to calculate and predict the relocation behavior of the debris bed under different experimental conditions, which further verified the applicability of the relocation onset model.
AB - When the core disruptive accident (CDA) occurs in the sodium-cooled fast reactor (SFR), the melted core fuel is cooled and solidified into debris particles by the coolant, which accumulates in the lower plenum and forms the debris bed. In order to effectively remove the decay heat from the debris bed and implement the in-vessel corium retention (IVR), it is necessary to predict and simulate the relocation behavior of the debris bed. For this reason, Zhang et al. developed an onset model for judging the relocation of the debris bed based on the force balance analysis of the particle. In this paper, a large number of debris bed relocation experiments were carried out by bottom gas-injection method, and the relocation onset model was used to calculate and predict the relocation behavior of the debris bed under different experimental conditions, which further verified the applicability of the relocation onset model.
KW - Bottom gas-injection experiment
KW - Model validation
KW - Relocation onset model
KW - Sodium-cooled fast reactor
UR - https://www.scopus.com/pages/publications/85099755127
U2 - 10.13832/j.jnpe.2021.01.0042
DO - 10.13832/j.jnpe.2021.01.0042
M3 - 文章
AN - SCOPUS:85099755127
SN - 0258-0926
VL - 42
SP - 42
EP - 47
JO - Hedongli Gongcheng/Nuclear Power Engineering
JF - Hedongli Gongcheng/Nuclear Power Engineering
IS - 1
ER -