TY - JOUR
T1 - Transient thermal-hydraulic analysis of a space thermionic reactor
AU - Zhang, Wenwen
AU - Ma, Zaiyong
AU - Zhang, Dalin
AU - Tian, Wenxi
AU - Qiu, Suizheng
AU - Su, G. H.
N1 - Publisher Copyright:
© 2015 Elsevier Ltd.
PY - 2016/3/1
Y1 - 2016/3/1
N2 - Nuclear power can serve as a durable energy source for future space exploitation and exploration. According to the special features of the space power system, a transient analysis code, TASTIN (Transient Analysis code of Space Thermionic Nuclear reactor), is developed to analyze the thermal-hydraulic characteristics of the TOPAZ-II system. The point reactor kinetics equations with six-family delayed neutrons are applied to calculate the fission power, considering the temperature reactivity feedback effects of the moderator, UO2 fuel, electrodes in the core and the reactivity insertion of control and safety drums. The thermal-hydraulic analysis of the core is carried out with multiple-channel model. A detailed tube-fin radiator model is also established and the finite difference method is used to calculate the conduction with radiation of the fin. The steady state calculation results are in good agreement with the design values. From both the partial loss of flow accident and the overpower transient, the moderator has the dominant temperature effect, account for positive reactivity temperature coefficient of the reactor. In addition, the results of the accidents above also prove that the reactor system has a sufficient safety margin during these typical accidents.
AB - Nuclear power can serve as a durable energy source for future space exploitation and exploration. According to the special features of the space power system, a transient analysis code, TASTIN (Transient Analysis code of Space Thermionic Nuclear reactor), is developed to analyze the thermal-hydraulic characteristics of the TOPAZ-II system. The point reactor kinetics equations with six-family delayed neutrons are applied to calculate the fission power, considering the temperature reactivity feedback effects of the moderator, UO2 fuel, electrodes in the core and the reactivity insertion of control and safety drums. The thermal-hydraulic analysis of the core is carried out with multiple-channel model. A detailed tube-fin radiator model is also established and the finite difference method is used to calculate the conduction with radiation of the fin. The steady state calculation results are in good agreement with the design values. From both the partial loss of flow accident and the overpower transient, the moderator has the dominant temperature effect, account for positive reactivity temperature coefficient of the reactor. In addition, the results of the accidents above also prove that the reactor system has a sufficient safety margin during these typical accidents.
KW - Space thermionic reactor
KW - TOPAZ-II
KW - Thermal-hydraulic analysis code
KW - Tube-fin radiator
UR - https://www.scopus.com/pages/publications/84947711077
U2 - 10.1016/j.anucene.2015.10.035
DO - 10.1016/j.anucene.2015.10.035
M3 - 文章
AN - SCOPUS:84947711077
SN - 0306-4549
VL - 89
SP - 38
EP - 49
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
ER -