TY - GEN
T1 - STEADY STATE AND TRANSIENT ANALYSIS OF GAS-COOLED REACTOR SPACE NUCLEAR POWER SYSTEM
AU - Zhang, Ran
AU - Guo, Kailun
AU - Wang, Chenglong
AU - Qiu, Suizheng
AU - Su, G. H.
N1 - Publisher Copyright:
© ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics.All rights reserved.
PY - 2020
Y1 - 2020
N2 - Space nuclear power system (SNPS) is an integral part of space nuclear systems. The high-temperature gascooled reactor coupled with Closed Brayton Cycle (CBC) can achieve high-power output. For this SNPS, a safety system analysis code is developed using Fortran. In the system code, the reactor model, turbinecompressor- alternator model, recuperator model, gas cooler model, heat pipes radiator model, pump model and pipe model are built. Then, the steady state calculation of system is performed using the code. The verification of this system code is provided via the comparison between the calculation results and the design values. Finally, the transient analysis under the accident condition, mechanical loss of one Brayton is carried out. The results show that the system is capable of keeping the power and temperature stable and below the safety limits due to the negative reactivity feedback of the fuel and the core block. This study could provide suggestions and guidance to the design and safety analysis of space nuclear power.
AB - Space nuclear power system (SNPS) is an integral part of space nuclear systems. The high-temperature gascooled reactor coupled with Closed Brayton Cycle (CBC) can achieve high-power output. For this SNPS, a safety system analysis code is developed using Fortran. In the system code, the reactor model, turbinecompressor- alternator model, recuperator model, gas cooler model, heat pipes radiator model, pump model and pipe model are built. Then, the steady state calculation of system is performed using the code. The verification of this system code is provided via the comparison between the calculation results and the design values. Finally, the transient analysis under the accident condition, mechanical loss of one Brayton is carried out. The results show that the system is capable of keeping the power and temperature stable and below the safety limits due to the negative reactivity feedback of the fuel and the core block. This study could provide suggestions and guidance to the design and safety analysis of space nuclear power.
KW - Closed Brayton Cycle
KW - Gas-cooled reactor
KW - SNPS
KW - Steady state and transient analysis
UR - https://www.scopus.com/pages/publications/85141509525
M3 - 会议稿件
AN - SCOPUS:85141509525
T3 - ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics
SP - 494
EP - 503
BT - ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics
PB - American Nuclear Society
T2 - 2020 International Topical Meeting on Advances in Thermal Hydraulics, ATH 2020
Y2 - 20 October 2020 through 23 October 2020
ER -