Salt chemistry and Redox control Jinsuo Zhang 1,2 1) Virginia Tech - - PowerPoint PPT Presentation

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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


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Salt chemistry and Redox control

Jinsuo Zhang1,2 1) Virginia Tech 2) Ohio State University

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

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 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

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Salt impurities/source term

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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)

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

What do we have to do

qReview the available data qMeasure fundamental data of element in the salt and liquid Bi qDevelop chemical (redox) control method qDevelop and design salt purification system in

  • peration

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Measurement-experimental set up

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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,

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Determining of reference potential

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Temperature (ยฐC)

๐‘ญ๐‹+ ๐‹

โ„ ๐ฌ๐Ÿ๐ž๐ฉ๐ฒ (V vs. Pt)

Standard Deviation (mV) 650

  • 1.272

3.2 700

  • 1.270

2.9 750

  • 1.271

4.6

Electrolyte resistance of 0.12 โ„ฆโˆ™cm2 at 650หšC, 0.11 โ„ฆโˆ™cm2 at 700หšC and 0.09 โ„ฆโˆ™cm2 at 750หšC

650หšC

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

  • surface. More negative potential

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.

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Measured CV signal

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Diffusion coefficient and Apparent potential of Dy and La

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Diffusion activation energy: 51.5 kJ/mol for Dy3+, 127 kJ/mol for La3+ Both diffusion coefficient and apparent potential increases with temperature

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Fundamental data of Corrosion Products

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Exchange current density of Fe and Cr

  • Activation energy: 94.42 kJ/mol for Cr/Cr2+, and

87.69 kJ/mol for Fe/Fe2+ in molten FLiNaK

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Redox Control

qCover gas control method qMetal control method qDissolved salt control method qRefueling control method qCathodic protection

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Dissolved Salt control method

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Tungsten electrode, 700หšC, FLiNaK-EuF3-EuF2, 200 mV/s

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Concentration ratio of Eu3+/Eu2+

  • Randles-Sevcik equation is not valid for system containing both

members (e.g., both U4+ and U3+)) of the redox couple: ๐‘—" = 0.4463๐‘œ๐บ๐ท,๐ธ./0 ๐‘œ๐บ๐‘ค ๐‘†๐‘ˆ

./0

  • Theory developed by Keightley et al. are adopted [1]:
  • ๐šฅ

โƒ— = ๐‘œ๐บ ๐ท,

789๐ธ789 ./0 + ๐ท, ;<๐ธ;< ./0 =>? @A ./0

๐œ“ ๐œŠ; ๐œŠE

  • ๐šฅ

โƒ– = ๐‘œ๐บ ๐ท,

789๐ธ789 ./0 + ๐ท, ;<๐ธ;< ./0 =>? @A ./0

[๐œ“ 2๐œŠI โˆ’ ๐œŠ, ๐œŠE โˆ’ ๐œ“ 2๐œŠI โˆ’ ๐œŠ, ๐œŠI โˆ’ ๐œ“ โˆ’๐œŠ, ๐œŠI ]

  • where ๐œ“ ๐‘ฆ, ๐›ฝ =

9P/Q 9RP/Q . 0 S

  • tanh

RYZ

โˆ’ tanh(

Z 0) ; ๐œŠ = ๐‘œ๐บ(๐น โˆ’ ๐น./0)/๐‘†๐‘ˆ

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[1] A.M. Keightley, et al, J. Electroanal. Chem. 322 (1992) 25-54.

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Determined concentration ratio

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Predicted coordinates of cyclic voltammetric peaks and the calculated concentration ratio. Test # ๐’๐‘ฎ ๐‘บ๐‘ผ โˆ†๐‘ญ๐ช ๐‘ซ๐…๐ฏ๐Ÿ‘+ ๐‘ซ๐…๐ฏ๐Ÿ’+ .๐‘ฌ๐…๐ฏ๐Ÿ‘+ ๐‘ฌ๐…๐ฏ๐Ÿ’+ 0๐’‹๐’’0 ๐‘ซ๐’„ . ๐‘บ๐‘ผ ๐’๐Ÿ’๐‘ฎ๐Ÿ’๐’˜๐‘ฌ๐’„

๐’๐‘ฎ ๐‘บ๐‘ผ(๐‘ญ๐Ÿ/๐Ÿ‘ โˆ’ ๐‘ญ๐’’ ๐’…) ๐‘ซ๐…๐ฏ๐Ÿ’+ ๐‘ซ๐…๐ฏ๐Ÿ‘+โ€ 

  • 2.236

0.4463 1.109

  • 650ยฐC #1

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.

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

XPS examination

  • Eu3+/Eu2+ ratio โ‰ˆ 2:1

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Formal potential for Eu3+/Eu2+

  • ๐นโˆ— = ๐น./0 + @A

=> ๐‘š๐‘œ `ab `cde

P Q

16 Temperature (ยฐC) E* (V vs. F2/F-) Salt Total concentration of Eu in salt Source 550

  • 3.94 or -3.82โ€ 

FLiNaK 0.072 mol/kg [1] 650

  • 3.836 ยฑ 0.005

FLiNaK 0.048 mol/kg This work 700

  • 3.787 ยฑ 0.009

FLiNaK 0.048 mol/kg This work 750

  • 3.732 ยฑ 0.006

FLiNaK 0.048 mol/kg This work 800

  • 3.53 ยฑ 0.01

LiF-CaF2 0.100 mol/kg [2] 820

  • 3.46 ยฑ 0.01

LiF-CaF2 0.100 mol/kg [2] 840

  • 3.40 ยฑ 0.01

LiF-CaF2 0.100 mol/kg [2] 870

  • 3.33 ยฑ 0.01

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

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Redox potential window

  • Solid line: metal dissolution at limit

activity of 10-6

  • Dotted line: reduction of oxidants.

HF/H2 =0.1: a mole ratio of HF/H2 =0.1 at 1 atm total pressure

  • Double solid line: redox potential

calculated based on measured apparent potential.

  • All potentials calculated based on โˆ†๐ปยฐ
  • f fluorides at supercooled state

except gaseous MoF5, MoF6, WF6, and HF.

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Acceleration mechanisms of Cr Dissolution

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Schematic of the direct reduction of the corrosion products on the cathode during galvanic corrosion. Ox represents the residual

  • xidants.

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

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Salt Purification Method

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q Bi-Li Extractor q Sacrificial Electrode

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Available Fundamental data in Liquid

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

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More fundamental data development based on phase diagram model

Bi-Ce

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

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Fundamental data of Fission products in liquid Bi-Enthalpy of mixing

Bi-Ce

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

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Activity coefficient of Fission products in liquid

923 K 973 K 873 K

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Purification model for Using Bi-Li

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| ๐‘œE๐‘Œ~โ€ข

โ‚ฌโ€ขโ€ข

โ€š

๐ถ๐‘—โ€žโ€ฆโ€ฆโ€  + ๐‘‡๐‘๐‘š๐‘ขโ€žโ€ฆโ€ฆโ€ ๐ธ~โ€ข

ล  Eโ€น.

= ๐‘

  • E

โ€š ๐ธโ€ขE โˆ’ ๐‘Œโ€ขEโ€ข โ€š

๐ถ๐‘—โ€žโ€ฆโ€ฆโ€  + ๐‘‡๐‘๐‘š๐‘ขโ€žโ€ฆโ€ฆโ€ ๐ธโ€ขE

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

One Example

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

E-pO2- diagram development

700C in FLiBe. ๐’ƒ๐๐จโ€ข of 10-6 is used for the calculation of related equilibrium lines

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pO(2-)

  • 2

2 4 6 8 10 12 14

E(V)

  • 4
  • 3.5
  • 3
  • 2.5
  • 2
  • 1.5
  • 1
  • 0.5

Cerium species in LiF-BeF2 at 723K

CeF3 Ce Ce2O3 pO(2-)

  • 2

2 4 6 8 10 12 14

E(V)

  • 4
  • 3.5
  • 3
  • 2.5
  • 2
  • 1.5
  • 1
  • 0.5

Plutonium species in LiF-BeF2 at 723K

PuF3 Pu2O3 Pu

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Chloride Salt Chemistry

q Nd, Gd, and La for high concentration up to 9wt% in KCl-LiCl

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La3+ Gd3+ Nd2+

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Nuclear Materials and Fuel Cycle center Nuclear Materials and Fuel Cycle center

Questions?

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