TY - GEN
T1 - Comparative study of basic reactor physics of the DFR concept using U-PU and TRU fuel salts
AU - Wang, Xiang
AU - Macian-Juan, Rafael
N1 - Publisher Copyright:
© Copyright 2017 ASME.
PY - 2017
Y1 - 2017
N2 - The Dual Fluid Reactor (DFR) is a molten salt fast reactor developed by the IFK1 based on the Gen-IV Molten-Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor (SFR, LFR) concepts. The analysis reported focuses on the comparison between previous neutronic calculations with the default fuel salt of UPu mixture and new ones with a transuranium (TRU) salt fuel option under steady state conditions. They include criticality, neutron spectrum, spatial flux distribution and temperature coefficient values. Fuel based on molten TRU salts has already been considered for the MSFR and other molten salt reactor designs. Therefore, the DFR for the first time has a comparable baseline with other molten salt reactors, so that its performance with TRU salt fuel can be assessed.
AB - The Dual Fluid Reactor (DFR) is a molten salt fast reactor developed by the IFK1 based on the Gen-IV Molten-Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor (SFR, LFR) concepts. The analysis reported focuses on the comparison between previous neutronic calculations with the default fuel salt of UPu mixture and new ones with a transuranium (TRU) salt fuel option under steady state conditions. They include criticality, neutron spectrum, spatial flux distribution and temperature coefficient values. Fuel based on molten TRU salts has already been considered for the MSFR and other molten salt reactor designs. Therefore, the DFR for the first time has a comparable baseline with other molten salt reactors, so that its performance with TRU salt fuel can be assessed.
UR - https://www.scopus.com/pages/publications/85032472808
U2 - 10.1115/ICONE2566035
DO - 10.1115/ICONE2566035
M3 - Conference contribution
AN - SCOPUS:85032472808
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
PB - American Society of Mechanical Engineers (ASME)
T2 - 2017 25th International Conference on Nuclear Engineering, ICONE 2017
Y2 - 2 July 2017 through 6 July 2017
ER -