TY - GEN
T1 - TRANSIENT THERMAL SAFETY ANALYSIS OF NUSTER-100 REACTOR CORE
AU - Jinlu, Huang
AU - Zhixing, Tian
AU - Chenglong, Wang
AU - Kailun, Guo
AU - Dalin, Zhang
AU - Wenxi, Tian
AU - Suizheng, Qiu
AU - Guanghui, Su
N1 - Publisher Copyright:
© 2023 by JSME.
PY - 2023
Y1 - 2023
N2 - The transient thermal safety characteristics of the NUSTER-100 were analyzed by applying the commercial CFD software FLUENT. The program module of the point reactor neutron kinetic model was developed through the user-defined function (UDF), coupled with the transient analysis code of heat pipe, and the transient thermal safety analysis of the NUSTER-100 was carried out. According to the power distribution of core obtained by MCNP, the 1/8 core physical model of NUSTER-100 was established. The operating conditions of the NUSTER-100 core and the single/multiple heat pipe failure accidents are analyzed. The results show that NUSTER-100 has good safety; the failure of a single heat pipe has a small impact on the core, and failure of two or more heat pipes may have a greater impact on the core. This article can provide methods and ideas for transient thermal analysis of the heat pipe cooled reactor.
AB - The transient thermal safety characteristics of the NUSTER-100 were analyzed by applying the commercial CFD software FLUENT. The program module of the point reactor neutron kinetic model was developed through the user-defined function (UDF), coupled with the transient analysis code of heat pipe, and the transient thermal safety analysis of the NUSTER-100 was carried out. According to the power distribution of core obtained by MCNP, the 1/8 core physical model of NUSTER-100 was established. The operating conditions of the NUSTER-100 core and the single/multiple heat pipe failure accidents are analyzed. The results show that NUSTER-100 has good safety; the failure of a single heat pipe has a small impact on the core, and failure of two or more heat pipes may have a greater impact on the core. This article can provide methods and ideas for transient thermal analysis of the heat pipe cooled reactor.
KW - Heat pipe cooled reactor
KW - Heat pipe failure accident
KW - point reactor kinetics
KW - thermal analysis
UR - https://www.scopus.com/pages/publications/85178503588
M3 - 会议稿件
AN - SCOPUS:85178503588
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables
PB - American Society of Mechanical Engineers (ASME)
T2 - 30th International Conference on Nuclear Engineering, ICONE 2023
Y2 - 21 May 2023 through 26 May 2023
ER -