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Comparative Study of Thermal-Hydraulic Behavior of the DFR Using U-Pu and TRU Salt Fuels

[+] Author Affiliations
Xiang Wang, Rafael Macian-Juan

Technical University of Munich, Garching, Germany

Paper No. ICONE25-66061, pp. V006T08A004; 10 pages
doi:10.1115/ICONE25-66061
From:
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 6: Thermal-Hydraulics
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5784-7
  • Copyright © 2017 by ASME

abstract

The Dual Fluid Reactor 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. Based on previous researches an analysis focusing on the simulation on different dimensions of the DFR system with transuranium (TRU) salt fuel option is performed. The zero-dimensional point-kinetics model coupled with the zero-dimensional heat-transfer model constructed by SIMULINK will be set up first. The radial power profile of the fuel salts inside of the fuel tube cell is described by a two-dimensional system which focuses on the single fuel unit cell of the DFR with the equivalent cylindrical model instead of the original hexagonal prismatic shape. The comparison between the results is then discussed.

Copyright © 2017 by ASME
Topics: Fuels

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