A promising fuel for fast neutron spectrum Molten Salt Reactor: NaCl-ThCl4-PuCl3

被引:4
作者
Dumaire, T. [1 ]
Ocadiz-Flores, J. A. [1 ]
Konings, R. J. M. [1 ,2 ]
Smith, A. L. [1 ]
机构
[1] Delft Univ Technol, Fac Appl Sci, Radiat Sci & Technol Dept, Mekelweg 15, NL-2629 JB Delft, Netherlands
[2] European Commiss, Joint Res Ctr JRC, Karlsruhe, Germany
来源
CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY | 2022年 / 79卷
关键词
Molten Salt Reactor; Chloride salts; Fuel; Thorium; Plutonium; CALPHAD; SYSTEMS; HEATS; MODEL;
D O I
10.1016/j.calphad.2022.102496
中图分类号
O414.1 [热力学];
学科分类号
摘要
Chloride salts are considered a good alternative to fluoride salts as fuel carrier in the Molten Salt Fast Reactor concepts. The NaCl-ThCl4 -PuCl3 fuel salt solution seems very promising, with low melting temperature eutectic compositions, and the potential to be used in a breeder and burner type of reactor design. This work focuses on the first thermodynamic modeling assessment of the ThCl4 -PuCl3 binary system and the NaCl-ThCl4 -PuCl3 ternary system, using the CALPHAD (Computer Coupling of Phase Diagrams and Thermochemistry) method and the quasichemical formalism in the quadruplet approximation. The investigated system shows potential for a high flexibility with respect to composition at operating temperatures, which can be beneficial to accommodate the requirements on other essential fuel properties (e.g. neutronic and thermo-hydraulic).
引用
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页数:10
相关论文
共 48 条
  • [1] Akebi M., 1991, ATOMIC ENERGY SOC JA
  • [2] FactSage thermochemical software and databases
    Bale, C
    Chartrand, P
    Degterov, SA
    Eriksson, G
    Hack, K
    Ben Mahfoud, R
    Melançon, J
    Pelton, AD
    Petersen, S
    [J]. CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY, 2002, 26 (02): : 189 - 228
  • [3] Thermodynamic evaluation of the NaCl-MgCl2-UCl3-PuCl3 system
    Benes, O.
    Konings, R. J. M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2008, 375 (02) : 202 - 208
  • [4] Benes O, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 3: ADVANCED FUELS/FUEL CLADDING/NUCLEAR FUEL PERFORMANCE MODELING AND SIMULATION, P359
  • [5] Thermodynamic assessment of the LiF-NaF-ThF4-UF4 system
    Benes, O.
    Beilmann, M.
    Konings, R. J. M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2010, 405 (02) : 186 - 198
  • [6] Benes O., 2020, COMPREHENSIVE NUCL M, Vsecond, P609, DOI [10.1016/b978-0-12-803581-8.11790-4, DOI 10.1016/B978-0-12-803581-8.11790-4]
  • [7] PHASE EQUILIBRIA IN THE BINARY SYSTEMS PUCL3-NACL AND PUCL3-LICL
    BJORKLUND, CW
    REAVIS, JG
    LEARY, JA
    WALSH, KA
    [J]. JOURNAL OF PHYSICAL CHEMISTRY, 1959, 63 (10) : 1774 - 1777
  • [8] Bychkov A.V., 1997, EXPT HIGH BURN UP FU
  • [9] Capelli E., 2020, Compr. Nucl. Mater, P256, DOI [DOI 10.1016/B978-0-12-803581-8.11794-1, 10.1016/b978-0-12-803581-8.11794-1]
  • [10] Phase diagram calculation: past, present and future
    Chang, YA
    Chen, SL
    Zhang, F
    Yan, XY
    Xie, FY
    Schmid-Fetzer, R
    Oates, WA
    [J]. PROGRESS IN MATERIALS SCIENCE, 2004, 49 (3-4) : 313 - 345