Salt chemistry and Redox control
Jinsuo Zhang1,2 1) Virginia Tech 2) Ohio State University
Salt chemistry and Redox control Jinsuo Zhang 1,2 1) Virginia Tech - - PowerPoint PPT Presentation
Salt chemistry and Redox control Jinsuo Zhang 1,2 1) Virginia Tech 2) Ohio State University Research Team q PI: Dr. Jinsuo Zhang, Dr. Shaoqiang Guo q Students: Ryan Chesser, Yafei Wang (graduated from OSU, current Ph.D student of VT), Qiufeng
Jinsuo Zhang1,2 1) Virginia Tech 2) Ohio State University
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
q PI: Dr. Jinsuo Zhang, Dr. Shaoqiang Guo q Students: Ryan Chesser, Yafei Wang (graduated from OSU, current Ph.D student of VT), Qiufeng Yang, Nik Shay (graduated), Bill Cohen (Graduated), Wentao Zhou (graduated), Evan Wu (graudated) q Visiting Scholar: Dr. Wei Wu All the experimental measurements presented were conducted at The Ohio State University
2
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
3
q Tritium q Noble Gas (Xe, Kr) q Noble metals (Nb, Mo, Tc, Ru, Rh, Ag, Cd, In, Sn, Zn, Ga, Ge, As ) q Halogens (I, Br) q Tellurium Group (Te, Sb, Se) q Barium, Strontium (Ba, Sr) q Rare earth/alkaline metals (Y, La, Ce, Pr, Nd, Pm, Gd, Tb, Dy, Ho, Er, Zr, Sm, Eu, Sr, Ba, Rb, Cs) q Actinide (U, Pu, Np) q Corrosion Products (Ni, Fe, Cr)
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
4
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
5
q A three-electrode system: working electrode (WE); Count electrode (CE) and Reference electrode (RE). q Glove box (purged with Argon): the O2 and H2O was controlled below 4.0 during all experiments. q Electrochemical technology: CV, EIS, LP, etc q Properties measured: apparent potential, diffusion coefficient, activity coefficient, exchange current,
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
6
Temperature (ยฐC)
๐ญ๐+ ๐
โ ๐ฌ๐๐๐ฉ๐ฒ (V vs. Pt)
Standard Deviation (mV) 650
3.2 700
2.9 750
4.6
Electrolyte resistance of 0.12 โฆโcm2 at 650หC, 0.11 โฆโcm2 at 700หC and 0.09 โฆโcm2 at 750หC
650หC
Zone I: 5s current pulse is applied, and the potential of the W electrode becomes more negative due to the formation of a potassium layer on electrode
at greater current due to the potential drop in electrolyte. Zone II: No current applied. Consistent potential represents K+/K potential. Zone III: Potential returns back due to dissolution of K.
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
7
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
8
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
9
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
10
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
11
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
12
Tungsten electrode, 700หC, FLiNaK-EuF3-EuF2, 200 mV/s
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
members (e.g., both U4+ and U3+)) of the redox couple: ๐" = 0.4463๐๐บ๐ท,๐ธ./0 ๐๐บ๐ค ๐๐
./0
โ = ๐๐บ ๐ท,
789๐ธ789 ./0 + ๐ท, ;<๐ธ;< ./0 =>? @A ./0
๐ ๐; ๐E
โ = ๐๐บ ๐ท,
789๐ธ789 ./0 + ๐ท, ;<๐ธ;< ./0 =>? @A ./0
[๐ 2๐I โ ๐, ๐E โ ๐ 2๐I โ ๐, ๐I โ ๐ โ๐, ๐I ]
9P/Q 9RP/Q . 0 S
RYZ
โ tanh(
Z 0) ; ๐ = ๐๐บ(๐น โ ๐น./0)/๐๐
13
[1] A.M. Keightley, et al, J. Electroanal. Chem. 322 (1992) 25-54.
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
14
Predicted coordinates of cyclic voltammetric peaks and the calculated concentration ratio. Test # ๐๐ฎ ๐บ๐ผ โ๐ญ๐ช ๐ซ๐ ๐ฏ๐+ ๐ซ๐ ๐ฏ๐+ .๐ฌ๐ ๐ฏ๐+ ๐ฌ๐ ๐ฏ๐+ 0๐๐0 ๐ซ๐ . ๐บ๐ผ ๐๐๐ฎ๐๐๐ฌ๐
๐๐ฎ ๐บ๐ผ(๐ญ๐/๐ โ ๐ญ๐ ๐ ) ๐ซ๐ ๐ฏ๐+ ๐ซ๐ ๐ฏ๐+โ
0.4463 1.109
2.814 1.31 0.5415 1.697 1.21 650ยฐC #2 3.102 2.13 0.5596 1.988 1.96 650ยฐC #3 3.075 2.04 0.5581 1.959 1.88 700ยฐC #1 2.855 1.42 0.5447 1.741 1.29 700ยฐC #2 3.067 2.02 0.5578 1.953 1.83 700ยฐC #3 3.119 2.18 0.5605 2.003 1.98 750ยฐC #1 2.740 1.13 0.5356 1.623 1.08 750ยฐC #2 2.674 0.98 0.5299 1.558 0.93 750ยฐC #3 2.842 1.39 0.5439 1.729 1.33 โ Calculated by the determined diffusion coefficient.
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
15
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
=> ๐๐ `ab `cde
P Q
16 Temperature (ยฐC) E* (V vs. F2/F-) Salt Total concentration of Eu in salt Source 550
FLiNaK 0.072 mol/kg [1] 650
FLiNaK 0.048 mol/kg This work 700
FLiNaK 0.048 mol/kg This work 750
FLiNaK 0.048 mol/kg This work 800
LiF-CaF2 0.100 mol/kg [2] 820
LiF-CaF2 0.100 mol/kg [2] 840
LiF-CaF2 0.100 mol/kg [2] 870
LiF-CaF2 0.100 mol/kg [2]
Table Summary of formal standard potential from this work and references
[1] W. Huang, et al. Electrochimi. Acta 147 (2014) 114-120. [2] L. Massot, et al. Electrochimi. Acta 54 (2009) 6361-6366
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
activity of 10-6
HF/H2 =0.1: a mole ratio of HF/H2 =0.1 at 1 atm total pressure
calculated based on measured apparent potential.
except gaseous MoF5, MoF6, WF6, and HF.
17
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
18
Schematic of the direct reduction of the corrosion products on the cathode during galvanic corrosion. Ox represents the residual
q Galvanic Corrosion q Direct reduction of Cr2+
Cathode (graphite): Cr0Y + 3 7 C + 2es โ 1 7 CrvCw
q Disproportionation reaction of Cr2+
Anode: Cr (alloy 1) โ Cr0Y + 2es Cathode (Ni): Cr0Y + 2es โ Cr (alloy 2) 3Cr0Y โ 2CrwY + Cr 3Cr0Y + 3 7 C โ 2CrwY + 1 7 CrvCw
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
19
q Bi-Li Extractor q Sacrificial Electrode
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
20
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
21
Bi-Ce
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
22
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
23
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
24
โฌโขโข
โ
ล Eโน.
โ ๐ธโขE โ ๐โขEโข โ
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
25
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
700C in FLiBe. ๐๐๐จโข of 10-6 is used for the calculation of related equilibrium lines
26
pO(2-)
2 4 6 8 10 12 14
E(V)
Cerium species in LiF-BeF2 at 723K
CeF3 Ce Ce2O3 pO(2-)
2 4 6 8 10 12 14
E(V)
Plutonium species in LiF-BeF2 at 723K
PuF3 Pu2O3 Pu
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
27
La3+ Gd3+ Nd2+
Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center
28