TY - GEN
T1 - Accident analysis of heat pipe cooled space reactor
AU - Yuan, Yuan
AU - Shan, Jianqiang
AU - Zhang, Bin
AU - Gou, Junli
AU - Zhang, Bo
PY - 2015
Y1 - 2015
N2 - A space power with high power density, light weight, low cost and high reliability is of crucial importance to future exploration of deep space. Space reactor is an excellent candidate because of its unique characteristics of high specific power, low cost, strong environment adaptability and so on. Among all types of space reactors, heat pipe cooled space reactor, which adopts the passive heat pipe as core cooling component, is considered as one of the most promising choice and is widely studied all over the world. A transient analysis code (TAPIRS) for heat pipe cooled space reactor power system is developed. The TAPIRS based on point reactor kinetics model, lumped parameter core heat transfer model, combined heat pipe (HP) model (self-diffusion model, flat-front startup model and network model), energy conversion model of alkali metal thermal-to-electric conversion units (AMTEC). and HP radiator model. Three typical accidents, i.e., control drum failure, AMTEC failure and partial loss of the heat transfer area of radiator arc then analyzed using TAPIRS. The results show that the heat pipe cooled space reactor has excellent inherent safety characteristics.
AB - A space power with high power density, light weight, low cost and high reliability is of crucial importance to future exploration of deep space. Space reactor is an excellent candidate because of its unique characteristics of high specific power, low cost, strong environment adaptability and so on. Among all types of space reactors, heat pipe cooled space reactor, which adopts the passive heat pipe as core cooling component, is considered as one of the most promising choice and is widely studied all over the world. A transient analysis code (TAPIRS) for heat pipe cooled space reactor power system is developed. The TAPIRS based on point reactor kinetics model, lumped parameter core heat transfer model, combined heat pipe (HP) model (self-diffusion model, flat-front startup model and network model), energy conversion model of alkali metal thermal-to-electric conversion units (AMTEC). and HP radiator model. Three typical accidents, i.e., control drum failure, AMTEC failure and partial loss of the heat transfer area of radiator arc then analyzed using TAPIRS. The results show that the heat pipe cooled space reactor has excellent inherent safety characteristics.
KW - AMTEC
KW - Accident
KW - Heat pipe
KW - SpacE reactor
UR - https://www.scopus.com/pages/publications/84964058349
M3 - 会议稿件
AN - SCOPUS:84964058349
T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
SP - 4961
EP - 4971
BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PB - American Nuclear Society
T2 - 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Y2 - 30 August 2015 through 4 September 2015
ER -