Tritium Transport in LLE: Investigations in the TITAN Collaboration

1. Tritium Transport in LLE: Investigations in theTITAN Collaboration P. Sharpe, P. Calderoni, D.-K. SzeS. Konishi, S. Fukada, T. Teraiand the TITAN Task 1-2 Team FNST Meeting UCLA 12-14 August 2008

2. OUTLINE LLE Database of Materials Properties Tritium Transport Data Variation Recent TITAN Task 1-2 Results Upcoming Work in TITAN Task 1-2

3. LLE Database of Materials Properties • Strong interest by several parties in the utility of LLE (lead-lithium eutectic) for fusion blanket systems • ITER TBM designs - DFLL (CN), HCLL (EU), DCLL (US) • Advanced reactor concepts - ARIES (US), European Fusion PowerPlant Design Options Studies, etc. • Varying functional demands on LLE - tritium breeding and some degree of self-cooling • Nuclear systems licensing requirements must be considered for LLE • Pedigree of database, maturity of materials properties, applicationof codes and standards • ITER TBM’s will be licensed separately from ITER • A coordinated effort is underway to establish a Computing Expert System Database for LLE thermo-physical/chemical properties; intended international availability • Database incorporates uncertainty quantification and degree of consensus (e.g. different experiment techniques to obtain property values)

4. LLE Database of Materials Properties, cont. Database classification: General Design Parameters and Ranges on Interest E and B fields - 0-1 kV/m, 0-15 T Neutron wall loading - 2.5 MW/m2Power density - ~1MW/m36Li burnup - ~ 0.1 at.% / fpd / GWthTemperature - 235˚C to 700˚CT pressure - 10 Pa to 10 kPaFlow velocity - ~ 1 mm/s to ~1 m/s LLE Materials Standard Database (Bulk) constitutive relations, thermodynamic properties,impurity characterization and behavior, chemical reactivity,H-isotope transport,and He bubble transport LLE Materials Extended Database (MHD) electric-magnetic properties,hydrodynamic correlations,and 2-phase dispersion correlations Near-eutectic Composition Sensitivities • LLE chemical activity governed by Li activity • Tritium solubility variation from mixture disproportioning in cool areas or aggregation • Mixture standards and impurity tolerances

5. Tritium Transport Data Variations courtesy L. Sedano, CIEMAT

6. Tritium Transport Data Variations, cont. Diffusion Constant Variations: Measurements from Desorption Technique D=2.32x10‑7exp(‑27000/RT) m2s‑1 Fukada’s recent data (Terai) (2) D=4.03x10‑8 exp(‑19500/RT) m2s‑1 (Reiter) (3) D=2.62x10‑9 exp(‑6630/RT) m2s‑1 (Shibuya) (4) D(450°C)= 1.5×10‑9 m2s-1 (Fauvet & Sannier) Moderate agreement - within an order of magnitude - from similar experiment arrangements. However sensitivity of D to mass transport correlations is needed for blanket system characterization. courtesy I. Ricapito, ENEA CR Brasimone

7. Temperature, ˚C 727 560 440 350 282 225 Absorption techniques Fukada Aiello Desorption techniques No consensus on data range, nor even behavior at low partial pressure… Tritium Transport Data Variations, cont. Sievert’s Constant Variations: courtesy I. Ricapito, ENEA CR Brasimone

8. Recent TITAN Task 1-2 Results • adsorption/desorption isothermmeasurement system installed at INL • Small quantities of LLE (~ 25g) testable inadsorption and desorption modes…

9. Recent TITAN Task 1-2 Results, cont. Solubility Variations: Preliminary data

10. 400 C 300 C 500 C 600 C Recent TITAN Task 1-2 Results, cont. Solubility Variations: Increasing temperature dashed - Aiello (adsorption) points - INL desorption data solid - Reiter (desportion) Solubiltiy (y-axis) expressed as concentration (atomic fraction) of hydrogen in LLE Plotted as x-axis is p - p expressed in Pa and covering the range 1 - 1x105 Pa

11. Ar Low pressure side Molecular diffusion recombination LiPb Atomic diffusion Fe High pressure side Molecular diffusion H2 or D2 dissociation Li-Pb Fe Recent TITAN Task 1-2 Results, cont. Solubility Variations: Fukada’s data • Test system assembled at Kyushu University; based on previous previous permeation tests in fusion liquid (Flinak and Flibe)

12. Recent TITAN Task 1-2 Results, cont. Solubility Variations: Fukada’s data

13. Upcoming Work in TITAN Task 1-2 • Testing of INL experiment using tritium • Testing of Kyushu experiment in bouyant convection configuration • Initiate design of LLE flow loop for testing T removal (vacuum permeator concept) Thank you for your attention!

14. LLE Database references (via Luis Sedano, CIEMAT)

15. Now for a blatant sales pitch…. but something that could benefit the US FNST endeavor…

16. The ATR National Scientific User Facility Primary U.S. nuclear technology R&D facility, with primary emphasis on fuels and materials Focal point for nuclear energy related expertise for the nation INL facilities plus select partnerships optimize utilization of national assets Through the ATR NSUF, INL strengthen its role as a center for advanced nuclear research in the U.S.

17. Building Capability to Meet User Needs New reactor capabilities (2008 - 2010) Hydraulic shuttle irradiation system operational by beginning of FY-09 Pressurized water loop for industry experiments in 2010 Test Train Assembly Facility commissioned in 2009 New PIE capabilities (2008 - 2010) Electron probe micro-analyzer (EPMA) Focused Ion Beam (FIB) Micro x-ray diffraction Mechanical testing in cell Scanning Thermal Diffusivity Crack Growth Testing Need for capability validated through industry advisory committee (ANIAC), user workshops and surveys, and Scientific Review Board (SRB)

18. Advanced In-reactor Instrumentation Measurement Examples Dimension Conductivity Material flaws Potential Technologies Fiber optics (cracks, temperature, etc.) Ultrasonic techniques (cracks, temperatures, length changes) SiC (temperature) Wireless technologies (temperature, pressure, etc.) Strategy Collaborate with Halden, Jules Horowitz, and Bettis LDRD funding used for advanced concepts Leverage capabilities developed using DOE program (GNEP, NGNP) and WFO funding. Collaborate with small business by participating in SBIRs AGR-1 Test Capsule Installed in ATR with INL HTIR-TCs Focused internal funding on instrumentation to improve ATR capability

19. 2008 University Experiments In FY 2009, an additional 4 - 5 experiments are planned and will offer the following: At least one instrumented lead experiment A wider range of positions available for experiments Potential for collaboration at university facilities All carry 2-4 year mortgages

20. What distinguishes ATR from Office of Science User Facilities? ATR NSUF is a comparable unique national asset, but does present unique management challenges (for operations and users)

21. Cooperate with Other U.S. and International Research Institutions, including NUC, to Meet ATR NSUF Objectives Capability of the ATR NSUF can be expanded through strategic partnerships University or laboratory research reactors University or laboratory hot cells or hot laboratories University or laboratory accelerator facilities Other national user facilities (APS, SHaRE) ATR NSUF will be the hub for nuclear fuels and materials irradiation/PIE, with nodes at other research institutions’ and universities’ research facilities.