Recent Progress in Flibe Chemistry Control, Corrosion, and Tritium Behavior Phil Sharpe Fusion Safety Program Idaho National Laboratory, USA HAPL Program Meeting ORNL 21-22 March 2006
Jan 27, 2016
Recent Progress inFlibe Chemistry Control, Corrosion, and Tritium
Behavior
Phil SharpeFusion Safety Program
Idaho National Laboratory, USA
HAPL Program Meeting
ORNL
21-22 March 2006
Fusion Safety Program
Slide 2
• Research Program Logic
• Purification
• Mobilization
• REDOX
• Corrosion
• Deuterium/tritium PermeationBehavior in Flibe
Topics for Review
Fusion Safety Program
Slide 3
Integrated Program Logic for Flibe Activities
FlibePurification
REDOXTritium
Experiments
Corrosion Tests
Interim Set Of Impurities
Is REDOX working?
Reducing TF?Able to Establish
Viable TritiumControl
Strategy? Is Corrosion
Acceptable?
Successful REDOXTritium Control and
Acceptable Impurities
Need To reduce Impurities
yes
yesno
yes
yes
Iteration loop is not in program because
of budget limitation
Preparation of Starting Materials
Fusion Safety Program
Slide 4
Flibe Purification and AnalysisHydro-fluorination approach
• Bubble H2/HF/He thru melt (530ºC)
• Chemical reactions
BeO + 2HF = BeF2 + H2O
MF2 + H2 = M + 2HF
Chemical Analysis of Flibe
• Components
• Pre- post- purification
• Techniques:Metals: ICP-AES, ICP-MS, dissolutionC, N, O: LECO
O(ppm)
C(ppm)
N(ppm)
Fe(ppm)
Ni(ppm)
Cr(ppm)
BeF2 5700 <20 58 295 20 18
LiF 60 <20 78 100 30 4
Flibe 560 10 32 260 15 16
Control instruments & He-HF gas cabinet
Pot/heater assemblyTitration cellGas manifoldsHF traps
ProcessedFlibe
Fusion Safety Program
Slide 5
Experiments on Flibe mobilization in Ar, air and humid air were completed. Obtained vapor pressures and mobilization estimates. Observed interesting behavior of the salt in different air and crucible environments
Mobilization Studies
Fusion Safety Program
Slide 6
Mobilization Studies, cont.
1.E-05
1.E-04
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
1.E+05
400 600 800 1000 1200 1400
Temperature (°C)
Pressure BeF
2 (Pa)
ORNL data [1]ORNL extrapolationOlander, et al. [2]INEEL argon dataINEEL moist airINEEL air data
Differential manometer
1.E-05
1.E-04
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
1.E+05
400 600 800 1000 1200 1400
Temperature (°C)
Vapor Pressure (Pa)
ORNL data [1]ORNL extrapolationOlander, et al. [2]Buchler & Stauffer [4]INEEL Total pressureINEEL-BeF2INEEL LiBeF3
Differential manometer
Mass Spectrometry
• Approach: Expose molten Flibe to Ar, air, moist air at 500-800ºC, quantify and characterize mobilized material
• Tests in argon agree with Knudsen mass spec data but are less than ORNL extrapolations and calculations
• Mobilized deposits were analyzed by ICP-AES. Vapor pressures were derived assuming BeF2 and LiBeF3 vapor species
• Tests in air and moist air show no significant differences from tests in argon
Fusion Safety Program
Slide 7
• Flibe under neutron irradiation will generate free fluorine and/or TF which can be quite corrosive
• Need to control fluorine potential to minimize corrosion
• Use Beryllium as the redox agent to tie up the free fluorine
• BeF2 has the lowest free energy of formation for all metal fluorides except LiF. Thus, BeF2 is the most stable with respect to other metal fluorides and TF as well
• Be is also useful for neutron multiplication in a blanket system.
Fluoride Potential
-1200
-1000
-800
-600
-400
-200
0
450 550 650 750
Temperature (°C)
-RTlnp
F2
(kJ/mole)
CeF3/CeF4
NiF2
H2/HF=10
FeF2
H2/HF =20/lowpressure H2
CrF2
Si2F6
MnF2
AlF3
BeF2
LiF
Flibe REDOX Control Studies- Needs
Fusion Safety Program
Slide 8
Flibe REDOX Control Studies- Rationale
T+
F-
n+LiF
Metal Wall, M
Be+ (surface or dissolved)
M (surface)
Key issue is chemical competition between T+, Be+ and metal wall for the free fluorine. REDOX control is expected to tie up F- and minimize formation of TF and MF
• Reactor calculations by DK Sze and APEX team suggest F- and/or TF concentration would be ~ 10 wppb per pass in the reactor
• This level corresponds to ~ 10 Pa which is 10-100 times below measurement sensitivity
• Evaluate REDOX behavior of Be in Flibe at different concentration levels of HF
• Evaluate Be solubility behavior in Flibe
• Develop kinetics model to guide experiments at very low HF level that are more representative of fusion blanket conditions
• Establish data needed for key checkpoint prior to tritium/corrosion testing
Fusion Safety Program
Slide 9
Flibe REDOX Control Studies- Approach• Three key reactions:
Be +2HF <--> BeF2+ H2
H2 + MF2 <--> M + 2HFHF(g) <--> HF(s)H2(s) <--> H2(g)
• Inject HF into the Flibe and measure change in HF in the outlet gas as a signature of the REDOX potential
• Insert Be rod into Flibe for a specified time and then remove
• If Be solubility in Flibe is enough to provide REDOX control, then HF will be converted to H2. If not, then REDOX is controlled by H2/HF reaction itself and we would expect to see no change in the gas
Inject HF
into the Flibe
• On line measurement of HF in the gas with titrator and mass spectrometer allows dynamic time dependent information to be obtained
• Can change HF level, temperature, Be exposure time and see dynamic change in system
Measure HF in the gas phase as a signature of REDOX potential
Be rod
Fusion Safety Program
Slide 10
€
VdC
dt= h C sat −C(t)( ),C(0) = 0
Wt% Be = Wt% Be( )sat
1− e−ht /V( )
Simple Mass Transfer Model
Be Dissolution Kinetics: Preliminary Data
• Both titrator and QMS used to estimate Be concentration in the salt after dunking with comparable results
• Even after 1 hr, the Be concentration is an order of magnitude less than that measured from dissolution test samples
• Need long term Be dunk in redox system to more accurately determine Csat in the model
0
0.00005
0.0001
0.00015
0.0002
0.00025
0.0003
0.00035
0 10 20 30 40 50 60 70
time (min)
maximum X(Be) from titrator data
from QMS data
Series3
Linear (Series3)
Fusion Safety Program
Slide 11
Times on the plot are Be exposure times
0
200
400
600
800
1000
1200
1400
0 10 20 30 40 50 60 70
time (hr)
HF concentration (ppm)
REDOX-4
REDOX-5
REDOX-6
REDOX-7
REDOX-10
10 min
20 min
30 min 60 min
Redox Results: HF Concentration vs time
• Be dunked in the salt for varying lengths of time
• HF concentration in the gas phase measured via QMS
• HF feed for these experiments was nominally 1000 ppm
• HF is initially reacted almost entirely by the Be
• As Be is depleted via reaction with HF, reaction rate slows
Fusion Safety Program
Slide 12
REDOX Results: HF conversion versus time
• HF conversion, f, is defined by:
• High conversion while Be remains immersed in Flibe
• Reduction in conversion as Be dissolved in Flibe is consumed
• Shape of curve is “inverted S”
€
f =1−yHFout (t)
yHFin
0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1
0 10 20 30 40 50 60 70
time (hr)
HF conversion
redox-6 (60 min)
redox-6 fit
redox-7 (30 min)
redox-7 fit
redox-8 (45 min)
redox-8 fit
redox-10 (20 min)
redox-10 fit
redox-11 (45 min)
redox-11 fit
redox-9 (1800 ppm, 30min)redox-9 fit
Fusion Safety Program
Slide 13
Simple REDOX Kinetics Modelingℜ=kyHFxBereaction rate plug flowreactor
f =1−e−αxBe
empirical relationship
relationship between xBe and time
• First attempt at a model neglected mass transfer limitations, rather assuming the kinetics are effectively reaction limited.
• The data best fit a reaction rate law first order in HF and Be, coupled with an unmixed reactor.
• Latest results appear to suggest that the reaction is in fact limited by diffusion of HF into the salt. The model is, thus, being reworked.
Fusion Safety Program
Slide 14
• When plotted in this dimensionless terms (f vs. xBe), the results are remarkably consistent
• Conversion (f) is based on mass spec data and Be mole fraction (xBe) is from titrator data
• Model predicts results very well
• Lower HF concentration data is currently being used to improve the model.
0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1
0 0.00005 0.0001 0.00015 0.0002
X(Be)
HF conversion
redox-6 data
redox-7 data
redox-8 data
redox-9 data
redox-10 data
redox-11 data
1st order, PFR fit
Simple REDOX Kinetics Modeling- Results
Fusion Safety Program
Slide 15
Corrosion Tests in Flibe
TC
He+H2+HF
HeHe
He
He
He+H2+HF
Pot-arrangement corrosion tests (stagnant fluid):
Fusion Safety Program
Slide 16
Planned Corrosion Tests
• Baseline Redox test with 5-hour Be exposure.HF=1075 ppmv, H2/HF=11, Flow Rate=140 sccmMeasure HF output with QMS and by titrationDissolve salt for H2 release, i.e., Be metal content
• Test with 5-hour Be dunk, then expose ferritic steelSample salt, ICP analyses for Fe, Cr, W and NiContinue test beyond Be Redox control point
• Remove metallic impurities by electrodeposition Test another ferritic steel coupon without the Be Redox pretreatment.
• Post-test Analyses: fracture, clean and examine sample by various methods, e.g., SEM, AES, XPS, XRD, and RBS
Fusion Safety Program
Slide 17
Exposure and Sampling Probesfor Corrosion Tests
Test positions for Be and FS sampleDepth of exposure: 2.3 cm
Fusion Safety Program
Slide 18
Consideration of Insulating Material
-300
-250
-200
-150
-100
-50
0
50
100
150
200
0 200 400 600 800 1000 1200
Temperature (C)
?G, kJ/mole F
2
Al2O3ZrO2MgOCaO
1/2 ZrO2 + 2 HF(g) = 1/2 ZrF 4 + H2O(g)
1/3 Al 2O3 + 2 HF(g) = 2/3 AlF 3 + H2O(g)
MgO + 2 HF(g) = MgF 2 + H2O(g)
CaO + 2 HF(g) = CaF 2 + H2O(g)
HF reactions with ceramics oxides
Alumina was selected.
Fusion Safety Program
Slide 19
Redox vs Corrosion Parameters
Be samplefor Redox tests
Diameter: 0.76 cmDepth: 1.9 cmArea: 4.99 cm2
Diameter: 0.51 cmDepth: 2.3 cmArea: 3.87 cm2
Be samplefor corrosion tests
Redox vs Corrosion
HF (ppm) = 500F.R. = 120 sccm
H2/HF = 10HF input rate=4.6E-8 mol/s
HF (ppm) = 1075F.R. = 140 sccm
H2/HF = 11HF input rate=1.12E-7 mol/s
Fusion Safety Program
Slide 20
Analyses of Salt Samples
Salt Sample: ~1.3 grams
Sulfuric acid dissolutions:H2 release, i.e.,
Be metal determinations
Nitric acid dissolutions:ICP-AES determinations
For Fe, Cr, W and Ni
~ 1 gram ~ 0.3 gram
Fusion Safety Program
Slide 21
Be Determinationed from Acid Tests
Acid Dissolutions of Flibe
0.001
0.010
0.100
1.000
10.000
0.00 0.20 0.40 0.60 0.80 1.00 1.20
Sample size (g)
Be metal in salt (mol%)
Detection liitBe6 saltBE10CenterBE10EdgeRedox test
(Redox 1-h test)
0.000
0.050
0.100
0.150
0.200
0.250
0 2 4 6 8 10 12
Be dunk time (h)
Be in salt (mol%)
Be Solubility
Fusion Safety Program
Slide 22
Chemical Analyses of Flibe following FS exposure
0
200
400
600
800
1000
1200
0 20 40 60 80 100 120
time (h)
Iron content (ppm)
REDOX control active
with REDOX control
w/o REDOX control
passivation or saturation
Flibe Batch: 475 g (14.7 moles)
Size of salt sample: 1.4 gram
Ferritic steel sample: Composition: 89Fe-9Cr-2W Exposed area: 0.65 cm2
Increase in salt: ppm-(g)Assuming uniformsample loss: (um) Fe Cr W
5 40-(0.019) 4 (0.002) 1 (0.0004)10 80 (0.037) 8 (0.004) 2 (0.0008)50 400 (0.185) 40 (0.019) 9 (0.004)
100 800 (0.370) 80 (0.037) 18 (0.008)500 4000 (1.850) 400 (0.187) 88 (0.042)1000 8000 (3.700) 800 (0.374) 175 (0.083)
ICP-AES det. limits (ppm) 10 10 10
Predicted increases of Fe in Flibe
Fusion Safety Program
Slide 23
Post-test Examination of FS Samples
FS sample with flibe coating
Weigh and fracture sample
Bottom section (INL) (re-weigh)
SEM of cross-section:Flibe to salt interface
Remove flibe: molten KCl:LiCl,then rinse with water, re-weigh
Surface analyses at INL:SEM, XPS and AES
Measure loss in thickness
Top section (Japanese) (re-weigh)
Baseline samples(thickness, mass)
Send to Japan:XRD, RBS, XPS and
Moessbauer analysis
Fusion Safety Program
Slide 24
Permeation experiments:Interrelated transport processes and chemical interactions characterize the behavior of hydrogen isotopes in molten salts
Integral test approach:
Dual permeation probes assembly
Combine experiment and modeling
• One-dimensional diffusion
• Nickel probes(0.5 mm) are Flibe resistant
• Diffusion in Flibe is rate-limiting
• 400 cc of Flibe
• Tests at 600 and 650ºC
Transport parameters
Diffusion, solubility, convection in melt
Recombination at metal surfaces
Liquid/gas phase transport
Chemical interactions
HT or HF
Trapping of T at impurities
Fusion Safety Program
Slide 25
Results of experiments: without/with Flibe
1013
2
3456
1014
2
3456
1015
1.31.21.11.00.9
1000/T [K-1]
800 700 600 500
Robertson's correlation
Ni, t=0.5mmD2 introduction
P=1.23x1017exp(-50.5/RgT)
one-probe exp two-probe exp
0 100 200 300 400 500 600 700 800
Elapsed time (min)-reference to PB1 pressurization
0
100
200
300
400
500
600
700
800
900
1000
D2
Partial pressure (Pa)-Exp A (no Flibe)
0
10
20
30
40
50
60
70
80
90
100
D2
Partial pressure (Pa)-Exp B (with Flibe)
Evacuate PB1
Exp B
Evacuate PB1
Exp A
Above Flibe(D2)
Exp B
Probe2(D2)
Exp B
Probe2(D2)
Exp A
Test temperature: 600oCExp A: no Flibe
Probe1 D2 pressure:
9.4x104 Pa
Probe2 Ar flow: 25 sccm
Pot volume Ar flow:
ET< 150 min: 0 sccm
ET> 150 min: 100 sccm
Exp B: with Flibe
Probe1 D2 pressure:
9.1x104 Pa
Probe2 Ar flow: 25 sccm
Ar flow above Flibe: 25 sccm
Without Flibe Without & with Flibe
Derived permeabilities in empty pot show good agreement with Robertson’s correlation for Ni
Reduction in probe-2 concentration of D2
(due to low solubility in Flibe)Time delay for observation of permeation signal in probe 2 (due to slow diffusivity in flibe)
D2 P
artia
l Pre
ssur
e
D2 P
artia
l Pre
ssur
e
Fusion Safety Program
Slide 26
Correlation of D diffusivity and solubility in Flibe
0.80 1.00 1.20 1.40 1.60 1.80
Inverse temperature (1000/K)
10 -14
10 -13
10 -12
10 -11
10 -10
10 -9
10 -8
10 -7
10 -6
Diffusion coefficient (m
2/s)
400500600700800Temperature ( oC)
Ohmichi et al. (F self diffusion)
Moriyama et al. (T in solid Flibe)
Stokes-Einstein
JUPITER-II (this work)
from D2 buildup
in Probe2
Oishi et al. (T)
Ed = 128 kJ/mol
En = 31 kJ/mol
Ed = 111 kJ/mol
Ed = 44 kJ/mol
0.90 1.00 1.10 1.20 1.30 1.40
Inverse temperature (1000/K)
10 -8
10 -7
10 -6
10 -5
10 -4
10 -3
Solubility coefficient (mol/m
3-Pa) 500600700800
Temperature ( oC)
JUPITER-II (this work)
from D2 buildup
in probe 2
Malinauskas et al. (H2, D2)
Field et al. (DF)
Diffusion data• > D from viscosity estimate• < D from capillary experiment• activation E similar to F- diffusion
Solubility dataDerived solubilities are comparableto those reported by Field et al. for DF in Flibe
Sol
ubil i
ty C
o ef fi
c ie n
t
Diff
usio
n C
oeffi
cien
t (m
2/s)
Fusion Safety Program
Slide 27
Activity 1: Installation and testing of permeation chamber in pot furnace arrangement
Activity 2: TMAP modeling of permeation chamber
Activity 3: Design of tritium handling and diagnostics systems
Activities for theFLiBe Tritium Permeation Experiment
Fusion Safety Program
Slide 28
Activity 1: Setup of Permeation Pot
• Permeation chamber received from Japan in October 2005; testing revealed pinhole leaks in several welds, repairs were made
• Chamber is designed to fit within pot furnace placed in glovebox; same system used for D2 permeation studies
• Salt bath is optional if thermal gradients persist or wall leakage is substantial
• New batch of Flibe is being prepared; hydro-fluorination purification to proceed following completion of corrosion studies
Ni10060.32.82215010Ni30956.3512.76.359.52NiNiss3162409.52lid ss316114160306.35φ6.35 φ6.35 φ316ss12.720446.352411010812
replace photo with one showing GC- for SCM
Fusion Safety Program
Slide 29
D2,, T2 orAr gas in Flibe in ExhaustAr gas in Ar gas out
Flibe stagnant
Ni
Electric furnace
High temperaturesalt
s.s.316
Activity 2: TMAP modeling of Permeation Chamber
• Straightforward modeling tool will help optimize experiment layout, e.g. required sweep gas flow rates, need for use of salt bath, thickness of Flibe for appropriately timed experiments, etc.
• 1-D axial model with sink terms to simulate radial loss of T
• Builds on success of TMAP modeling with D2 permeation experiment
• Suitable study for graduate student, but need to perform soon
Model basis for permeation pot by Fukada et al.
Fusion Safety Program
Slide 30
Activity 3: Design and testing of tritium handling anddiagnostics systems
• Tritium provided in pressurized vessel containing D2/T2 mixture
• Glovebox setup to contain potential leaks
• Localized tritium cleanup will be connected
• GC column for H isotope separation has been tested with tritium; works well but needs calibration
• Develop DF/TF generator if schedule permits
Ar D2
Flow meter
Flow meter
Flow meter
Gas chromatograph
or QMS
or ionization chamber
HF trap
exhaust
High temperature salt
Flinak or Flibe
Cap
Ni
T2
Vacuum pump
Pressure gauge
dip Be if Redox control is successful
Conceptual layout proposed by Fukada et al.