TY - JOUR
T1 - Experimental research on assembly section stiffness and bending stiffness for sodium-cooled fast reactor
AU - Ma, Zehua
AU - Yang, Hongyi
AU - Ma, Zhenhui
AU - Wu, Yingwei
AU - Lu, Kailin
AU - Wang, Kaiqiang
AU - Chen, Hongen
AU - Su, G. H.
AU - Chen, Zhenmao
N1 - Publisher Copyright:
© 2019 Elsevier Ltd
PY - 2020/1
Y1 - 2020/1
N2 - China Fast Reactor (CFR) is under construction, and the section stiffness and bending stiffness of CFR assemblies remain unknown and need to be investigated to support the core restraint system design and reactivity safety assessment. In this study, assembly compression tests were performed with three types of test samples. With the compression load varying from 0 to 6 kN, the compressive deformations were measured and the section stiffness were obtained. In assembly bending tests, there were two types of assemblies considering different spike clearances, and the horizontal loads from 400 N to 1900 N were applicable to the upper-load-pad, lower-load-pad and mid-fissile-region level of the assemblies. Assembly deflections were measured and correlations for the load-deflection ratio were proposed. Comparison of theoretical and experimental bending stiffness were carried out, which indicated that the spike clearance has to be taken into consideration in the assembly deformation analysis codes.
AB - China Fast Reactor (CFR) is under construction, and the section stiffness and bending stiffness of CFR assemblies remain unknown and need to be investigated to support the core restraint system design and reactivity safety assessment. In this study, assembly compression tests were performed with three types of test samples. With the compression load varying from 0 to 6 kN, the compressive deformations were measured and the section stiffness were obtained. In assembly bending tests, there were two types of assemblies considering different spike clearances, and the horizontal loads from 400 N to 1900 N were applicable to the upper-load-pad, lower-load-pad and mid-fissile-region level of the assemblies. Assembly deflections were measured and correlations for the load-deflection ratio were proposed. Comparison of theoretical and experimental bending stiffness were carried out, which indicated that the spike clearance has to be taken into consideration in the assembly deformation analysis codes.
KW - Assembly bending stiffness
KW - Assembly deformation analysis
KW - Assembly section stiffness
KW - Fast reactor
UR - https://www.scopus.com/pages/publications/85070991862
U2 - 10.1016/j.anucene.2019.106994
DO - 10.1016/j.anucene.2019.106994
M3 - 文章
AN - SCOPUS:85070991862
SN - 0306-4549
VL - 135
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 106994
ER -