Post on 28-Aug-2020
Hydrogen Isotope Transport in the Graphitic Fuel Elements of Fluoride-Salt Cooled High-Temperature Reactors (FHR)
Raluca O. Scarlat
Nuclear Engineering, UW Madison raluca.scarlat@wisc.edu
Nuclear Engineering Colloquium University of California Berkeley
26 October 2015
HEATandMASS.ep.wisc.edu���
Outline
1. Reflections on Year 1 as an Assistant Professor 2. Overview of FHR technology and related research at
UW Madison 3. Tritium management in the FHR 4. Tritium transport in the salt-graphite system
Raluca Scarlat | HEATandMASS.ep.wisc.edu 2
Reflections on Year 1 as an Assistant Professor
3 Raluca Scarlat | HEATandMASS.ep.wisc.edu
1. Recruiting a
research group 2. Learning a (or at
least one) new field 3. Developing courses 4. Establishing a
laboratory 5. Writing grants 6. Training students 7. Envisioning the
future
4 Raluca Scarlat | HEATandMASS.ep.wisc.edu
Outline
1. Reflections on Year 1 as an Assistant Professor 2. Overview of FHR technology and related research at
UW Madison 3. Tritium management in the FHR 4. Tritium transport in the salt-graphite system
Raluca Scarlat | HEATandMASS.ep.wisc.edu 5
6
Pebble Bed FHR Mark 1 Core Design
Raluca Scarlat | HEATandMASS.ep.wisc.edu
“Technical Description of the "Mark 1" Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant.” UCBTH-14-002.
FHRs: Fluoride-Salt Cooled High-Temperature Reactors
Liquid fluoride salt coolants2LiF - BeF2 (flibe)
Coated particle fuel (“TRISO Fuel”)Embedded in a “Graphite Matrix”
Raluca Scarlat | HEATandMASS.ep.wisc.edu 7
“Ceramographic Examinations of Irradiated AGR-1 Fuel Compacts.” Sept. 2012. INL/EXT-12-25301. Revision 1
Freezing phenomenology: phase diagram
Freezing phenomenology: uncertainty in salt composition
F. Carotti, M. Abou Dbai, K. Ahmed, J. P. Kallas, E. Alkindi, Raluca O. Scarlat. Experimental and Modeling Studies of Over-Cooling Transients in Fluoride-Salt Cooled High-Temperature Reactors (FHR). NURETH-16: 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics. 30 Aug. – 4 Sept. 2015. Chicago, IL.
Nuclear Air-Brayton Combined Cycle (NACC)
Modified GE 7FA Turbine for Co-fired NACC Base-load power: 42% efficiency (100 MWe) Gas co-firing: 66% efficiency (242 MWe)
Raluca Scarlat | HEATandMASS.ep.wisc.edu 10
“Technical Description of the "Mark 1" Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant.” UCBTH-14-002.
Outline
1. Overview of FHR technology 2. Tritium management in the FHR 3. Tritium transport in the salt-graphite system 4. Ongoing work
Raluca Scarlat | HEATandMASS.ep.wisc.edu 11
Tritium Source Term in FHR ! The main sources of tritium production are Li-6 and Li-7
! Natural Li isotopic composition: 7.5% 6Li – 92.5% 7Li ! Target 6Li start-up concentration: 60 ppm 6Li ! Steady state 6Li concentration: 8 ppm 6Li
! Lithium-6 is continuously created:
! Natural Be isotopic composition: 100% 9Be
HeHLin 42
31
63
10 +→+ HnHenLi 3
110
42
10
73 ++→+
HeHeBen 42
62
94
10 +→+ eLiHe 0
163
62 −+→
0.0001$
0.001$
0.01$
0.1$
1$
10$
100$
1000$
10000$
0.00001$ 0.0001$ 0.001$ 0.01$ 0.1$ 1$ 10$ 100$ 1000$ 10000$ 100000$ 1000000$10000000$
Cross%S
ec)on%
(b)%
Energy%(eV)%
Cross Sections for (n,α) Reactions
1. http://www.nrc.gov/reactors/operating/ops-experience/tritium/faqs.html#normal 2. Ohashi, Hirofumi and Sherman, Steven R. Tritium Movement and Accumulation in the NGNP System Interface and Hydrogen Plant. s.l. : Idaho National Laboratory,
2007. INL/EXT-07-12746
g/year per GWe Ci/year per GWePB-FHR 176 1.7 x 106
PWR (average) 0.08 730CANDU (Darlington) 576 8.0 x 106
Tritium Source Term in FHR
0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 0.18
0 2 4 6 8
10 12 14
0 1 2 3 4 5 6 7 8 9 10 11
(mol
T/E
FPD
)
Triti
um P
rodu
ctio
n R
ate
(Ci/
EFP
Y)
Effective Full Power Years
Estimated Tritum Production Rate in the Mk1 PB-FHR Core
FHR Tritium Emission Design Goal (Based on tritium production at steady state flibe isotopic composition, per GWe)
! FHR production: (1.7)106 Ci/yr (176 g/yr)
! If 100% released to air: 10-5 Ci/kg air (0.5x10-7 NRC limit) ! Reduce by a factor of 200
! PWR emissions: (0.7)103 Ci/yr (0.075 g/yr) ! Reduce by a factor of 2000
Tritium Sinks and Sources in FHR
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Gas Sparging Studies at SINAP
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Outline
1. Overview of FHR technology 2. Tritium management in the FHR 3. Tritium transport in the salt-graphite system 4. Ongoing work
Raluca Scarlat | HEATandMASS.ep.wisc.edu 16
Perfect Sink Calculations
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Perfect Sink Calculations
Literature Data for Tritium Saturation in Graphite
Michael C. Young, Huali Wu, Raluca O. Scarlat. Characterization of Tritium Transport in the FLiBe-Graphite System, for In-Situ Tritium Absorption by the Fuel Elements of the Fluoride-Salt Cooled High-Temperature Reactor (FHR). NURETH-16: 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics. 30 Aug. – 4 Sept. 2015. Chicago, IL.
The Scientific Questions
! Goals: ! How much tritium will be retained in an FHR fuel pebble? ! How long will it take for the pebble to reach equilibrium tritium concentration?
! Studies: ! What is the “rate-limiting step” for tritium absorption into the fuel elements? ! What is the mechanism of tritium transport and trapping in matrix graphite? ! What are the interface mechanisms that contribute to tritium transport? ! What are the effects of graphite irradiation damage? ! What data from nuclear graphite is relevant? ! What is the effect of salt intrusion? ! What are the desorption characteristics? ! What effects do salt chemistry and graphite pre-treatment have?
18 Raluca Scarlat | HEATandMASS.ep.wisc.edu
Ongoing Research Activities
1. Salt intrusion experiment 2. Contact angle measurements 3. Hydrogen absorption experiment 4. Matrix graphite characterization 5. Modeling tool for tritium transport in graphite 6. Electrochemical impedance spectroscopy
19 Raluca Scarlat | HEATandMASS.ep.wisc.edu
Background Information: MSRE
! ORNL-4865: Graphite stringers (CGB) from MSRE were analyzed for tritium with depth profiling. Contains information on FP distributions and transport.
! ORNL-5011: Small graphite samples were exposed to T2 gas and analyzed.
! Briggs (1972): Measured and calculated distributions of tritium in the MSRE.
! Does this data lend itself to useful benchmark exercises?
! If so, what assumptions about the MSRE and its operations limit application to FHR?
Comparison with MSRE Data Diffusion only
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Comparison with MSRE Data Diffusion and Trapping
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Trapping Model
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Matrix Graphite Characterization
Matrix Graphite Characterization
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Graphitization Process (http://www.graphiteconcept.com/content/view/33/27/)
Matrix Graphite Characterization Some Preliminary Results
Huali Wu | huali@wisc.edu | HEATandMASS.ep.wisc.edu | Slide 1
Goal: 1) To study mainly matrix graphite physical properties – density, porosity, pore distribution, surface area, graphitization; 2) To understand the difference between Matrix graphite and nuclear graphite
Graphite Characterization Property Technique IG-110 A3
Density (g/cc) Apparent Density 1.712 1.3868 Intruded Density 2.11 ― Gas Pycnometer 2.1468 ―
Porosity Numerical Calculation
BET(Krypton) ― ― Matlab Image Analysis 0.1778 0.1508
Pore Distribution Mercury Porosimetry See Slide- See Slide- Surface Area BET(Krypton) ― ―
Graphitization (d002) X-ray Diffraction 88.40% 75.60%
In-plane Crystalline Size(nm) Raman 19.653 20.883
Other Techniques SEM See Slide- See Slide-
Optical Microscopy See Slide- See Slide-
Matrix Graphite Characterization Irradiation Effects
26 Raluca Scarlat | HEATandMASS.ep.wisc.edu
Hydrogen Absorption Experiment Huali Wu
Huali Wu | huali@wisc.edu | HEATandMASS.ep.wisc.edu | Slide 1
Goal: to study hydrogen behavior in flibe-graphite system (saturation-limited or diffusion-rate-limited)
Constant Volume Method
Gas Cylinder
T Fittings
Leak Valve
Diaphragm Valve
GasReservoir
Diaphragm Vavlve
T Fittings VacuumGauge
Vacuum Pump
AbsolutePressure Gauge
T FittingsDifferentiaPressureGauge
T Fittings
Diaphragm Valve
Diaphragm Valve
Sample Container
Heating Tape
Insulation
Graphite Sample
! Two in-core irradiations completed: 300 and 1000 hours at 700°C ! Double-encapsulation with nickel inner vessel, graphite liner, titanium cold-wall ! 100-300g of MSRE secondary flibe ! Nuclear heating with ±3°C temperature control (He/Ne) ! Separate gas flows in each containment, tritium collected
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FHR Capsule Irradiations at the MIT Reactor
Raluca Scarlat | HEATandMASS.ep.wisc.edu
Electrochmical Techniques in Flibe Francesco Carotti
Jenkins et al. 1968
Used by: Dr.Straka et al. at UJV (Czech Republic)
Problems:• Never used for more than 80hrs• Reaction of Ni2+ ions with
boron nitrite (important at low concentrations)
• LaF3 difficult to machine? Expensive? Fragile?
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Research Topic 2: Salt Infiltration into Graphite
Huali Wu | huali@wisc.edu | HEATandMASS.ep.wisc.edu | Slide 1
Goal: to investigate salt infiltration in graphite: penetration depth, amount, and mechanism
Vertical Furnace
Graphite Crucible
Sample Holder
Pressure Release Hole
Sample (1200 grit polished & DI water ultrasonic cleaned) NG: 0.0915g MG: 0.0477g
Flibe Intrusion in Graphite Preliminary Results
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0
500
1000
1500
2000
2500
-0.25 0.25 0.75 1.25 1.75 2.25 2.75 3.25 mg/
kg [p
pm w
t]
Micrometers
Li (With Salt)
-1000.000
0.000
1000.000
2000.000
3000.000
4000.000
0 101 201 302 402 503
F pp
mw
t
Depth in microns
F vs depth
F ppmwt
detection limit
Matrix Graphite Characterization
Electron Microprobe Results Mass Spectroscopy
Summary of Ongoing Tritium Transport Work in the Scarlat Group
! Goals: 1. How much tritium will be retained in an FHR fuel pebble? 2. What are the dominant transport mechanisms relevant to FHR?
! Ongoing work: 1. Salt intrusion experiment 2. Contact angle measurements 3. Hydrogen absorption experiment 4. Matrix graphite characterization 5. Modeling tool for tritium transport in graphite 6. Electrochemical impedance spectroscopy
32 Raluca Scarlat | HEATandMASS.ep.wisc.edu
Thank you
33 Heat & Mass Transport Group | HEATandMASS.ep.wisc.edu