TY - JOUR
T1 - 倾斜条件对海上小型堆LOCA事故的影响研究
AU - Cao, Zhiwei
AU - Liu, Jianchang
AU - Xiao, Hong
AU - Yang, Jiang
AU - Lu, Xianghui
AU - Tian, Wenxi
N1 - Publisher Copyright:
© 2019, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
PY - 2019/10/15
Y1 - 2019/10/15
N2 - Based on the thermal-hydraulic system analysis code RELAP/SCDAPSIM, the models of the primary loop and secondary loop and the safety injection system of the small offshore reactor are built, and LOCA with a double ended break under different inclination angles are simulated. Simulation results show that, longitudinal inclination has little effect on thermal parameters of the reactor, while lateral inclination does have a significant influence, and steep edge effect exists. Particularly, when the lateral inclining with large angle occurs, there is a significant reduction of core water level due to the redistribution of liquid coolant in the primary loop, and peak cladding temperature of the fuel is raised about 520℃.
AB - Based on the thermal-hydraulic system analysis code RELAP/SCDAPSIM, the models of the primary loop and secondary loop and the safety injection system of the small offshore reactor are built, and LOCA with a double ended break under different inclination angles are simulated. Simulation results show that, longitudinal inclination has little effect on thermal parameters of the reactor, while lateral inclination does have a significant influence, and steep edge effect exists. Particularly, when the lateral inclining with large angle occurs, there is a significant reduction of core water level due to the redistribution of liquid coolant in the primary loop, and peak cladding temperature of the fuel is raised about 520℃.
KW - Break LOCA
KW - Inclination condition
KW - OTSG
KW - Small offshore reactor
UR - https://www.scopus.com/pages/publications/85077005330
U2 - 10.13832/j.jnpe.2019.05.0118
DO - 10.13832/j.jnpe.2019.05.0118
M3 - 文章
AN - SCOPUS:85077005330
SN - 0258-0926
VL - 40
SP - 118
EP - 123
JO - Hedongli Gongcheng/Nuclear Power Engineering
JF - Hedongli Gongcheng/Nuclear Power Engineering
IS - 5
ER -