TY - GEN
T1 - Dynamics and stability analysis of DFT using U-Pu and Tru fuel salts
AU - Wang, Xiang
AU - Liu, Chunyu
AU - Macián-Juan, Rafael
N1 - Publisher Copyright:
© 2018 American Nuclear Society. All rights reserved.
PY - 2018
Y1 - 2018
N2 - The Dual Fluid Reactor is a molten salt fast reactor developed by IFK (Institut fuer Festkoerper-Kernphysik) based on the Gen-IV Molten-Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor (SFR, LFR) concepts. This analysis report focuses on the comparison between previous coupled calculations of the system with the default fuel salt of U-Pu mixture and new one with a transuranium (TRU) fuel salt option. An approach to the dynamics and stability analysis of the DFR by using the welldeveloped linear method with their improved modifications is proposed. The coupled one-dimensional neutronics and thermal-hydraulic model will be established with this method. With this model the steady state and the dynamics analysis of the system under various operational conditions are presented. The stability of the system will be also analyzed with the results in the parametric studies. The results are compared with Molten Salt Breeder Reactor (MSBR) and Molten Salt Fast Reactor (MSFR), which can be decisive for the future application of the DFR.
AB - The Dual Fluid Reactor is a molten salt fast reactor developed by IFK (Institut fuer Festkoerper-Kernphysik) based on the Gen-IV Molten-Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor (SFR, LFR) concepts. This analysis report focuses on the comparison between previous coupled calculations of the system with the default fuel salt of U-Pu mixture and new one with a transuranium (TRU) fuel salt option. An approach to the dynamics and stability analysis of the DFR by using the welldeveloped linear method with their improved modifications is proposed. The coupled one-dimensional neutronics and thermal-hydraulic model will be established with this method. With this model the steady state and the dynamics analysis of the system under various operational conditions are presented. The stability of the system will be also analyzed with the results in the parametric studies. The results are compared with Molten Salt Breeder Reactor (MSBR) and Molten Salt Fast Reactor (MSFR), which can be decisive for the future application of the DFR.
UR - http://www.scopus.com/inward/record.url?scp=85050110629&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:85050110629
T3 - Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
SP - 460
EP - 468
BT - Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
PB - American Nuclear Society
T2 - 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
Y2 - 8 April 2018 through 11 April 2018
ER -